SEC Petition Evaluation Report

Petition SEC-00043

Report Rev # 1 Report Submittal Date February 5, 2008

Subject Expert(s): Ray Clark, Cindy Bloom, Leon Baker, Karin Jessen, Dan Stempfley 

Site Expert(s): N/A 

Petition Administrative Summary 

Petition Under Evaluation 

Petition # Petition Type Qualification Date DOE/AWE Facility Name 

SEC-00043 83.13 November 9, 2005 Chapman Valve Manufacturing Company 

Petitioner Class Definition 

Guards, captain of guards, chief inspectors, inspectors, engineers, master mechanics, heat treater foremen, steamfitters, 

machine repairers, assistant to director of research, steam fitting and plumbing maintenance foremen, machine shops and 

maintenance general superintendents, electricians, chief electricians, milling machine operators, centerless grinder 

operators, portable grinder machinists, chipper machinists, assemblers, tool crib machinists, turret lathe operators, janitors,

janitor helpers, decontamination workers, firefighters, and general foremen who worked at Chapman Valve 

Manufacturing Company in Indian Orchard, Massachusetts, from 1948 through 1949 and from 1991 through 1995 (DOE 

Remediation). 

Proposed Class Definition 

All AWE employees who were monitored, or should have been monitored, for radiological exposures while performing 

Atomic Energy Commission work at the Chapman Valve Manufacturing Company (i.e., Building 23 and the Dean Street 

facility) in Indian Orchard, Massachusetts, from January 1, 1948 through December 31, 1949, and from January 1, 1991 

through December 31, 1993. 

Related Petition Summary Information 

SEC Petition Tracking #(s) Petition Type DOE/AWE Facility Name Petition Status 

None 

Related Evaluation Report Information 

Report Title DOE/AWE Facility Name 

None 

ORAU Lead Technical Evaluator: Ray Clark ORAU Review Completed By: Dan Stempfley 

Peer Review Completed By: [Signature on file] 02/05/2008 

Mark Rolfes Date 

SEC Petition Evaluation Reviewed By: [Signature on file] 02/05/2008 

J. W. Neton Date 

SEC Evaluation Approved By: [Signature on file] 02/05/2008 

Larry Elliott Date 
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Evaluation Report Summary: SEC-00043, Chapman Valve 

This evaluation report by the National Institute for Occupational Safety and Health (NIOSH) 

addresses a class of employees proposed for addition to the Special Exposure Cohort (SEC) per the 

Energy Employees Occupational Illness Compensation Program Act of 2000, as amended, 42 USC 

(EEOICPA) and 42 CFR 83, Procedures for Designating Classes of Employees as Members of the 

Special Exposure Cohort Under the Energy Employees Occupational Illness Compensation Program 

Act of 2000. 

Petitioner Requested Class Definition

Petition SEC-00043, qualified on November 9, 2005, requested that NIOSH consider the following 

class: Guards, captain of guards, chief inspectors, inspectors, engineers, master mechanics, heat 

treater foremen, steamfitters, machine repairers, assistant to director of research, steam fitting and 

plumbing maintenance foremen, machine shops and maintenance general superintendents, 

electricians, chief electricians, milling machine operators, centerless grinder operators, portable 

grinder machinists, chipper machinists, assemblers, tool crib machinists, turret lathe operators, 

janitors, janitor helpers, decontamination workers, firefighters, and general foremen who worked at 

Chapman Valve Manufacturing Company in Indian Orchard, Massachusetts, from 1948 through 1949 

and from 1991 through 1995 (DOE Remediation). 

NIOSH Proposed Class Definition

Based on its research, NIOSH modified the petitioner-requested class to define a single class of 

employees for which NIOSH can estimate radiation doses with sufficient accuracy. This proposed 

class includes: All AWE employees who were monitored, or should have been monitored, for 

radiological exposures while performing Atomic Energy Commission work at the Chapman Valve 

Manufacturing Company (i.e., Building 23 and the Dean Street facility) in Indian Orchard, 

Massachusetts, from January 1, 1948 through December 31, 1949, and from January 1, 1991 through 

December 31, 1993. 

For the purposes of this evaluation, the period from January 1, 1948, through April 30, 1949, is 

evaluated as the operational period; the periods from May 1, 1949, through December 31, 1949, and 

from January 1, 1991, through December 31, 1993, are evaluated as residual radioactivity periods. 

The latter period of the petitioner- requested class was reduced from 1991 through 1995 to 1991 

through 1993 in order to expedite the evaluation of this SEC Petition. The 1994-1995 period will be 

evaluated as a Remediation Period and the development of a dose reconstruction method in the 

Chapman Valve Technical Basis Document for this period has been reserved pending further research. 

NIOSH is continuing to evaluate the 1994-1995 remediation period and available data for Chapman 

Valve, and will address this period in an addendum to this Evaluation Report. In addition, the 

building/facility designation in this evaluation was modified to include the Dean Street facility to be 

consistent with the DOE’s recent evaluation of the facility designation for Chapman Valve (Dean 

2008). 

 
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Feasibility of Dose Reconstruction

Per EEOICPA and 42 CFR § 83.13(c)(1), NIOSH has established that it has access to sufficient 

information to: (1) estimate the maximum radiation dose incurred by any member of the class; or (2) 

estimate radiation doses more precisely than a maximum dose estimate. Information available from 

the site profile and additional resources are sufficient to document or estimate the maximum internal 

and external potential exposure to members of the proposed class under plausible circumstances 

during the specified period. 

Health Endangerment Determination

Per EEOICPA and 42 CFR § 83.13(c)(3), a health endangerment determination is not required 

because NIOSH has determined that it has sufficient information to estimate dose for the members of 

the proposed class. 
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Table of Contents 

Evaluation Report Summary: SEC-00043, Chapman Valve................................................................... 3 

1.0 Purpose and Scope.......................................................................................................................... 7 

2.0 Introduction .................................................................................................................................... 7 

3.0 Petitioner Requested Class/Basis and NIOSH Proposed Class/Basis ............................................ 8 

4.0 Data Sources Reviewed by NIOSH................................................................................................ 9 

4.1 Site Profile/Technical Basis Documents (TBDs).................................................................. 9 

4.2 ORAU Technical Information Bulletins (OTIBs)............................................................... 10 

4.3 Facility Employees and Experts .......................................................................................... 10 

4.4 Previous Dose Reconstructions ........................................................................................... 11 

4.5 NIOSH Site Research Database .......................................................................................... 12 

4.6 Documentation and/or Affidavits Provided by Petitioners ................................................. 12 

5.0 Radiological Operations Relevant to the Proposed Class ............................................................ 13 

5.1 Chapman Valve Facility and Process Descriptions............................................................. 13 

5.2 Radiological Exposure Sources from Chapman Valve Operations..................................... 15 

5.2.1 Alpha Particle Emissions......................................................................................... 16 

5.2.2 Beta Radiation Fields .............................................................................................. 17 

5.2.3 Neutron Exposures .................................................................................................. 17 

5.2.4 Photon Exposures .................................................................................................... 17 

6.0 Summary of Available Monitoring Data for the Proposed Class................................................. 17 

6.1 Chapman Valve Internal Monitoring Data .......................................................................... 17 

6.2 Chapman Valve External Monitoring Data......................................................................... 18 

6.3 Chapman Valve Air Sampling Data.................................................................................... 19 

7.0 Feasibility of Dose Reconstruction for the Proposed Class ......................................................... 20 

7.1 Sufficiency of Chapman Valve Data................................................................................... 20 

7.1.1 Pedigree of Data ...................................................................................................... 21 

7.1.1.1 External Data Review............................................................................... 21 

7.1.1.2 Internal Data Review................................................................................ 22 

7.1.2 Credibility and Consistency of Data........................................................................ 22 

7.1.2.1 External Data Review............................................................................... 22 

7.1.2.2 Internal Data Review................................................................................ 23 

7.1.3 Data Sufficiency Conclusions ................................................................................. 24 

7.2 Internal Radiation Doses at Chapman Valve....................................................................... 26 

7.2.1 Process-related Internal Doses at Chapman Valve.................................................. 26 

7.2.1.1 Urinalysis Information and Available Data.............................................. 26 

7.2.1.2 Unmonitored Workers – Application of Co-Worker Data for Internal 

Dose Reconstruction................................................................................. 29 

7.2.2 Ambient Environmental and Residual Radioactivity Internal Radiation Doses ..... 29 
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7.2.3 Internal Dose Reconstruction Feasibility Conclusion ............................................. 30 

7.3 External Radiation Doses at Chapman Valve ..................................................................... 30 

7.3.1 Process-related External Radiation Doses at Chapman Valve ................................ 30 

7.3.1.1 Individual Dosimetry Data ....................................................................... 30 

7.3.1.2 Unmonitored Workers – Application of Co-Worker Data for External 

Dose Reconstruction................................................................................. 31 

7.3.2 Ambient Environmental and Residual Radioactivity External Radiation Doses .... 31 

7.3.3 Chapman Valve Occupational X-Ray Examinations .............................................. 32 

7.3.4 External Dose Reconstruction Feasibility Conclusion............................................ 32 

7.4 Evaluation of Petition Basis for SEC-00043....................................................................... 33 

7.4.1 Evaluation of Specific Petitioner Statements in SEC-00043 .................................. 33 

7.4.1.1 Available Uranium Bioassay Data ........................................................... 33 

7.4.1.2 Uranium Bioassay Data Detection Limits................................................ 33 

7.4.1.3 Estimation of an Upper Bound Dose........................................................ 34 

7.4.1.4 Estimation of Uranium Exposures from a Site Fire ................................. 35 

7.4.1.5 Estimation of Enriched Uranium Exposures ............................................ 35 

7.4.1.6 Consideration of Other Industrial Processes ............................................ 36 

7.4.1.7 Available Air Sampling Data ................................................................... 38 

7.4.1.8 Uranium Fires........................................................................................... 38 

7.5 Summary of Feasibility Findings for Petition SEC-00043.................................................. 38 

8.0 Evaluation of Health Endangerment for Petition SEC-00043...................................................... 39 

9.0 NIOSH Proposed Class for Petition SEC-00043.......................................................................... 39 

10.0 References .................................................................................................................................... 41 

Tables 

4-1: Chapman Valve Claims Submitted Under Dose Reconstruction Rule.......................................... 11 

5-1: Job Titles Associated with 1948 Chapman Valve Bioassay Samples ........................................... 18 

7-1: Comparison of Bioassay Data for Y-12, Simonds Saw and Steel, and Chapman Valve............... 24 

7-2: Bioassay Results from Co-worker Data......................................................................................... 27 

7-3: Inhalation Intakes Based on Co-worker Data ................................................................................ 28 

7-4: Inhalation Intake Summary for Operational Period....................................................................... 29 

7-5: Annual Internal Exposure to Residual Radioactivity..................................................................... 30 

7-6: External Exposure Summary for Operational Period .................................................................... 31 

7-7: Annual External Exposure to Residual Radioactivity.................................................................... 32 

7-8: Summary of Feasibility Findings for SEC-00043.......................................................................... 39 
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SEC Petition Evaluation Report for SEC-00043

1.0 Purpose and Scope 

This evaluation report documents the feasibility of reconstructing doses for all AWE employees 

who were monitored, or should have been monitored, for radiological exposures while performing 

Atomic Energy Commission work at the Chapman Valve Manufacturing Company (i.e., Building 23 

and the Dean Street facility) in Indian Orchard, Massachusetts, from January 1, 1948 through 

December 31, 1949, and from January 1, 1991 through December 31, 1993. It provides information 

and analyses germane to considering a petition for adding a class of employees to the congressionallycreated SEC. 

This report does not provide any determinations concerning the feasibility of dose reconstruction that 

necessarily apply to any individual energy employee who might require a dose reconstruction from 

NIOSH. This report does not document the final determination as to whether or not the proposed 

class will be added to the SEC (see Section 2.0). 

This evaluation was conducted in accordance with the requirements of EEOICPA, 42 CFR 83, and the 

guidance contained in the Office of Compensation Analysis and Support’s Internal Procedures for the 

Evaluation of Special Exposure Cohort Petitions, OCAS-PR-004. 

2.0 Introduction 

The EEOICPA and 42 CFR 83 require NIOSH to evaluate qualified petitions requesting the 

Department of Health and Human Services (HHS) to add a class of employees to the SEC. The 

evaluation is intended to provide a fair, science-based determination of whether or not it is feasible to 

estimate with sufficient accuracy the radiation doses for members of the proposed class of 

employees.1 

42 CFR § 83.13(c)(1) states: Radiation doses can be estimated with sufficient accuracy if NIOSH has 

established that it has access to sufficient information to estimate the maximum radiation dose, for 

every type of cancer for which radiation doses are reconstructed, that could have been incurred in 

plausible circumstances by any member of the class, or if NIOSH has established that it has access to 

sufficient information to estimate the radiation doses of members of the class more precisely than an 

estimate of the maximum radiation dose.

 

Under 42 CFR § 83.13(c)(3), if it is not feasible to estimate with sufficient accuracy radiation doses 

for members of the class, NIOSH must also make a determination whether or not there is a reasonable 

likelihood that such radiation doses may have endangered the health of members of the class. The 

regulation requires NIOSH to assume that any duration of unprotected exposure may have endangered 

 

1

 NIOSH dose reconstructions under EEOICPA are performed using the methods promulgated under 42 CFR 82 and the 

detailed implementation guidelines available at www.cdc.gov/niosh/ocas. 
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the health of members of a class when it has been established that the class may have been exposed to 

radiation during a discrete incident likely to have involved levels of exposure similarly high to those 

occurring during nuclear criticality incidents. If the occurrence of such an exceptionally high level 

exposure has not been established, then NIOSH is required to specify that health was endangered for 

those workers who were employed for at least 250 aggregated work days either solely under the 

employment or in combination with work days within the parameters established for other SEC 

classes (excluding aggregate workday requirements). 

NIOSH is required to document the petition evaluation in a report. For development of the evaluation 

report, NIOSH relies on its own dose reconstruction expertise as well as technical support from Oak 

Ridge Associated Universities Team (ORAUT). Upon completion, the report is provided to the 

petitioners and to the Advisory Board on Radiation and Worker Health. The Board will consider the 

NIOSH evaluation report, together with the petition, petitioner(s) comments, and other information 

the Board considers appropriate, to make recommendations to the Secretary of HHS on whether or not 

to add one or more classes of employees to the SEC. Once NIOSH has received and considered the 

advice of the Board, the Director of NIOSH will propose decisions on behalf of HHS. The Secretary 

of HHS will make final decisions, taking into account the NIOSH evaluation, the advice of the Board, 

and the proposed decisions and recommendations of the Director of NIOSH. Following this decision 

process, petitioners may seek a review of certain types of final decisions issued by the Secretary of 

HHS.2

 

3.0 Petitioner Requested Class/Basis and NIOSH Proposed Class/Basis 

Petition SEC-00043, qualified on November 9, 2005, requested that NIOSH consider the following 

class: Guards, captain of guards, chief inspectors, inspectors, engineers, master mechanics, heat 

treater foremen, steamfitters, machine repairers, assistant to director of research, steam fitting and 

plumbing maintenance foremen, machine shops and maintenance general superintendents, 

electricians, chief electricians, milling machine operators, centerless grinder operators, portable 

grinder machinists, chipper machinists, assemblers, tool crib machinists, turret lathe operators, 

janitors, janitor helpers, decontamination workers, firefighters, and general foremen who worked at 

Chapman Valve Manufacturing Company in Indian Orchard, Massachusetts, from 1948 through 1949 

and from 1991 through 1995 (DOE Remediation).

The petitioner provided information and affidavit statements in support of the petitioner’s belief that 

sufficiently accurate dose reconstruction over time is not possible because: (1) personnel were not 

monitored through personal or area monitoring; (2) monitoring records have been lost, falsified, or 

destroyed; or (3) there is no monitoring, source term, or process-related information for the site. 

NIOSH considered the following information and affidavit statements sufficient to qualify SEC-00043 

for evaluation. 

The documentation provided by the petitioner (SECIS document IDs: 9185 and 9248) in 

support of SEC petition 00043 (SECIS document ID: 9184) asserted that: (1) there were 

only three periods (33 samples) of available bioassay monitoring for the AEC contract 

 

2

 See 42 CFR 83 for a full description of the procedures summarized here. Additional internal procedures are available at 

www.cdc.gov/niosh/ocas. 
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period at Chapman Valve, and there is no data to support why these samples were 

collected; (2) there is insufficient data to support the determination of a plausible upper 

bound dose estimate (there is a lack of monitoring data and a lack of process and source 

term information); (3) there is insufficient data regarding a documented uranium fire in 

May-June 1948; (4) the Chapman Valve Site Profile does not account for the potential of 

enriched uranium; (5) the Chapman Valve Site Profile does not account for potential 

exposures at the cracking furnace and the uranium chip incinerator, or the potential for a 

uranium-rolling operation; and (6) there is only one day of uranium air-sample data; (7) 

there is no assumption in the Chapman Valve Site Profile to address the potential for 

uranium fires or the potential frequency of uranium fires. 

The information and statements provided by the petitioner qualified the petition for further 

consideration by NIOSH, the Board, and HHS. The details of the petition basis are addressed in 

Section 7.4. 

NIOSH modified the petitioner-requested class considered in this current evaluation report to include 

all AWE employees who were monitored, or should have been monitored, for radiological exposures 

while performing Atomic Energy Commission work at the Chapman Valve Manufacturing Company 

(i.e., Building 23 and the Dean Street facility) in Indian Orchard, Massachusetts, from January 1, 1948 

through December 31, 1949, and from January 1, 1991 through December 31, 1993. For the purposes 

of this evaluation, the period from January 1, 1948, through April 30, 1949 is evaluated as the 

operational period; the periods from May 1, 1949, through December 31, 1949, and from January 1, 

1991, through December 31, 1993, are evaluated as residual radioactivity periods. The latter period of 

the petitioner-requested class, from 1994 through 1995, will be evaluated as a Remediation Period. 

The development of a dose reconstruction method for this period in the Chapman Valve Technical 

Basis Document has been reserved pending further research. NIOSH’s evaluation of the 1994-1995 

remediation period, and the available data for Chapman Valve, will be addressed in an addendum to 

this Evaluation Report. In addition, the building/facility designation in this evaluation was modified 

to include the Dean Street facility to be consistent with the DOE’s planned update (Dean, 2008) to the 

Chapman Valve, Indian Orchard facility designation on the Office of Worker Advocacy facility list. 

 

4.0 Data Sources Reviewed by NIOSH 

NIOSH identified and reviewed data sources to determine the availability of information relevant to 

determining the feasibility of dose reconstruction for the class of employees proposed for this petition. 

This included determining the availability of information on personal monitoring, area monitoring, 

industrial processes, and radiation source materials. The following sections summarize the data 

sources identified and reviewed. 

4.1 Site Profile/Technical Basis Documents (TBDs) 

A Site Profile/Technical Basis Document provides specific information concerning the documentation 

of historical practices at the specified site. Dose reconstructors can use the Site Profile/Technical 

Basis Document to aid in the interpretation of internal and external personal monitoring data. The 

Site Profile/Technical Basis Document also provides methodologies for evaluating potential radiation 
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doses for unmonitored workers. It may serve as a supplement to, or substitute for, individual 

monitoring data. As part of this evaluation, the following TBD was reviewed: 

• Technical Basis Document: Basis for the Development of an Exposure Matrix for Chapman Valve 

Manufacturing, Indian Orchard, Massachusetts, Period of Operation: January 4, 1948 through 

April 30, 1949; ORAUT-TKBS-0033; February 22, 2005 

4.2 ORAU Technical Information Bulletins (OTIBs) 

An ORAU Technical Information Bulletin (OTIB) is a general working document that provides 

guidance concerning the preparation of dose reconstructions at particular sites or categories of sites. 

NIOSH reviewed the following OTIBs describing the dosimetry program at Chapman Valve, as well 

as the use of co-worker data to fill in gaps in monitoring information for some employees and 

timeframes: 

• OTIB: Dose Reconstruction from Occupationally Related Diagnostic X-Ray Procedures; 

ORAUT-OTIB-0006, Rev. 2; December 21, 2005

• OTIB: Estimating the Maximum Plausible Dose to Workers at Atomic Weapons Employer 

Facilities; ORAUT-OTIB-0004, Rev 03, November 18, 2005

4.3 Facility Employees and Experts 

NIOSH conducted phone interviews with four former Chapman Valve Manufacturing Company 

employees. The documented information associated with these interviews has been compiled in 

NIOSH’s SEC Information System (SECIS). The former employees were asked the following 

questions about the AEC operations related to uranium work at Chapman: 

1. Where did you work in the operation? Did you work in the set aside “nuclear/atomic area” of 

Building 23? 

2. Can you describe the operations in the nuclear area? Were the operations limited to uranium 

machining or were there uranium-rolling operations? 

3. Do you recall a furnace in the set aside area? Do you recall what it was used for? (Could it have 

been a cracking furnace or a chip incinerator?) 

4. Do you recall what they did with the nuclear scrap or turnings/shavings? 

5. Are there any other details you would like to add? 

All four individuals worked in the restricted area in Building 23 at Chapman Valve. As indicated 

from the interviews, their job titles/duties included work as a metalsmith in the maintenance group, 

work as a sandblaster/gritblaster/grinder, work in support of turning, cutting, milling, and drilling 

operations, and work as a crane rigger and equipment operator. The common consensus of the four 

interviewees was that, based on their recollection of the uranium operations at Chapman Valve, only 
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machining and grinding operations were performed. None of the interviewees could recall any 

operations associated with uranium rolling. There were varied responses regarding the existence of a 

‘cracking’ furnace at Chapman. Three of the four individuals recalled/discussed variations of a 

furnace “at the end of the building” with the description of operations ranging from an incinerator to a 

casting furnace to a heat-treatment furnace. 

The responses regarding the disposition of the scrap trimmings/shavings was inconclusive, although 

one interviewee stated that the chips/shavings/cuttings were placed in the furnace “and reheated to 

make additional product.” 

In addition to the phone interviews conducted with the four former employees, the comments and 

responses related to the Chapman Valve worker outreach meeting were reviewed for this report. The 

information provided in the documentation from this meeting, is generally consistent with the 

information/responses provided by the four interviewees discussed above. 

4.4 Previous Dose Reconstructions 

NIOSH reviewed its dose reconstruction database, NIOSH OCAS Claims Tracking System (NOCTS), 

to identify dose reconstruction cases under EEOICPA that might provide information relevant to the 

petition evaluation. As of May 1, 2006, NIOSH had received a total of 106 individual claims for the 

Chapman Valve Manufacturing Company that fell within the timeframe identified in the proposed 

class definition. Table 4-1 provides a results summary of this review for the January 1, 1948, through 

December 31, 1949; and from January 1, 1991, through December 31, 1993, timeframes. 

Table 4-1: Chapman Valve Claims Submitted Under Dose Reconstruction Rule 

(01-01-48 through 12-31-49; and 01-01-91 through 12-31-93) 

(Data available as of: May 1, 2006) 

Description Totals 

Total number of cases submitted for energy employees who meet the proposed class definition 

criteria 106 

Number of dose reconstructions completed for energy employees who were employed during the 

years identified in the proposed class definition 91 

Number of cases for which internal dosimetry records were obtained for the identified years in the 

proposed class definition 5 

Number of cases for which external dosimetry records were obtained for the identified years in the 

proposed class definition 9 

NIOSH reviewed each claim to determine whether internal and/or external personal monitoring 

records could be obtained for the employee. Computer Assisted Telephone Interviews (CATIs) were 

conducted with the intent of obtaining additional information relevant to the individual claim, such as 

work locations, hours, job titles, and other information. 
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As part of the dose reconstruction process, the CATIs were carefully reviewed for relevant 

information. To the extent that it related to the individual claims reviewed for this evaluation, the 

interviews provided some useful information for dose reconstructions (i.e., work locations, hours 

worked, and hazards encountered). 

4.5 NIOSH Site Research Database 

The NIOSH site research database was reviewed for documents to support the evaluation of the 

proposed class. This database contains some useful information for Chapman Valve, including: dose 

rate survey reports, film badge records, urinalysis data, radiological control program descriptions, air 

monitoring data, and process descriptions. 

4.6 Documentation and/or Affidavits Provided by Petitioners 

In qualifying and evaluating the petition, NIOSH reviewed the following documents submitted by the 

petitioners: 

1. Petition Form B and supporting information provided within the petition; SECIS document ID: 

9184; received August 23, 2005. 

2. E-mail correspondence dated April 22, 2005, petition-supporting documentation that includes job 

titles from urine data sheets (as Attachment 1); SECIS document ID: 9185; received August 23, 

2005. 

3. Map of Building 23, petition-supporting documentation cover sheet (as Attachment 2) and map (as 

separate document); SECIS document IDs: 9185 and 9338; received August 23, 2005, and 

November 21, 2005, respectively. 

4. Draft meeting minutes from NIOSH Dose Reconstruction Project Meeting on the Chapman Valve 

Site Profile conducted on February 14, 2005; petition-supporting documentation (as Attachment 

3); SECIS document ID: 9185; received August 23, 2005. 

5. Excerpt from Results of Radiological Survey at the Former Chapman Valve Manufacturing 

Company, Indian Orchard, Massachusetts (CIO001), ORNL/RASA-92/1, issued July 1992; R. D. 

Foley, M. S. Uziel; petition-supporting documentation (as Attachment 4); SECIS document ID: 

9185; received August 23, 2005. 

6. Memo from W. E. Kelly to Walter J. Williams, Date Unreadable, re: SF Materials Lost or 

Unaccounted For; petition-supporting documentation (as Attachment 5); SECIS document ID: 

9185; received August 23, 2005. 

7. Affidavit provided by the petitioner dated September 15, 2005 (directly related to the information 

provided in the Petition Form B); SECIS id: 9248; received September 23, 2005. 
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5.0 Radiological Operations Relevant to the Proposed Class 

The following subsections summarize the radiological operations at the Chapman Valve 

Manufacturing Company from January 1, 1948, to April 30, 1949; and the activities with the potential 

for residual radioactivity exposures from May 1, 1949, through December 31, 1949, and from January 

1, 1991, through December 31, 1993. These discussions include information available to NIOSH for 

characterizing the radiological processes and source terms during these periods. NIOSH has gathered 

information regarding the identity and quantities of the radionuclides of concern, the processes 

through which radiation exposures may have occurred, and the physical environment in which 

exposures may have occurred. The information included within this evaluation report is only a 

summary of the available information. 

5.1 Chapman Valve Facility and Process Descriptions 

The Chapman Valve Manufacturing Company was a principal supplier of regular and special valves 

and manifolds for the Manhattan Engineer District [MED] (Young, 1987). AEC (Y-12 Plant) 

contracts with Chapman identified to date include: W-22-0705-eng-64 [dated 1/5/49], W-7401-eng38, 136, and 137 [dated 4/20/48] (Contracts); and W-7412-eng-1 [1943 valve order] (Chapman, 

1943). Records also indicate that Chapman Valve, under contract with the Brookhaven Laboratory, 

machined uranium metal during the period January through November, 1948 (Young, 1987). 

The Chapman Valve main office and works were located on Hampshire Street in Indian Orchard, 

Massachusetts. Uranium shipments were made to Oak Street and claims refer to [uranium] operations 

in the building on Pine Vale Street (ORAUT-TKBS-0033). 

In 1947, Chapman set aside approximately one-third of Department No. 40 in the western end of 

Building 23 at the Chapman Plant Site, 203 Hampshire Street, Indian Orchard, Massachusetts, to 

engage in a uranium program for Brookhaven National Laboratory (BNL) (Chapman, 1996). This part 

of the facility was separated from the remainder of the building by a floor-to-ceiling wooden partition 

and measured approximately 200-feet long by 60-feet wide. The ceiling was more than 50-feet high 

(Dvorchak, 1987). 

To follow up on NIOSH and DOL EEOICPA inquiries, the DOE Office of Legacy Management 

performed additional research to determine whether radiological work was ever performed at the 

Chapman Valve - Dean Street location. The review and follow-up on this location was initiated (at 

least in part) because of a comment by a former Chapman Valve worker indicating possible additional 

sources of radioactive material that may call into question the Chapman facility definition and time 

frame determinations originally made by the DOE Office of Worker Advocacy (i.e., possible transfer 

point for manifolds from Oak Ridge for testing at Chapman Valve - Dean Street that may have 

contained enriched uranium). 

The DOE confirmed that the Manhattan Engineering District (MED) placed contracts with Chapman 

Valve to fabricate valves and manifolds for the Y-12 Electromagnetic Project. During its 

investigation, the DOE did not identify any documents or information to corroborate that additional 

sources of radioactive material were received or handled on behalf of the MED/AEC at the Chapman 

Valve - Dean Street facility. The DOE concluded that the Chapman Valve Manufacturing Company 
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held numerous contracts with the MED (Oak Ridge) and the War Department (Army/Navy) during, 

and immediately following, World War II to produce valve bodies and manifolds, and that the 

Chapman Valve - Dean Street building should be recognized as part of the Indian Orchard facility on 

the DOE OWA Facility List. However, the DOE also concluded that no additional sources of 

radioactive materials were identified and no MED/AEC-related radiological work could be identified 

at Chapman Valve other than what is currently listed by the DOE OWA (Dean, 2008). Based on the 

lack of any MED/AEC-identified and/or related radiological activities at the Chapman Valve - Dean 

Street facility, no further discussion and review of that location will be included in this evaluation. 

Correspondence pertaining to the radiological history of the site indicates that the AEC established a 

health and safety program at the Chapman facility. Workers in the AEC area of Building 23 were 

required to wear white coveralls and badges while in the special work area (Dvorchak, 1987). Area 

access controls were in place. These controls are not clearly associated with job categories, but were 

an issue of both security and contamination control. An affidavit from a former Chapman Valve 

employee describes some of the radiological safety controls (Ungerland, 1987). According to the 

affidavit, workers removed their clothes and donned white coveralls prior to entering the uranium 

manufacturing area. Workers wore dosimeters on their uniforms and inspectors passed through the 

site carrying Geiger counters. At the completion of a day’s work, the employees returned to the 

dressing room and removed their white coveralls. Each employee was then required to take a shower 

as a safety measure. 

Preparation for the BNL uranium machining effort may have begun in November, 1947, with the 

initiation of health and safety programs (Wolf, 1947). An inventory report indicated that Chapman 

Valve had less than 50 pounds of uranium as of January, 1948 (Morgan, 1948). Actual production 

may not have started until May, 1948, but a set of contamination measurements from March, 1948, 

indicates that start-up activities may have begun earlier (LeVine, 1948). Records indicate that 

machining operations ceased in November, 1948, and all identified uranium materials and scrap was 

sent off site before the end of the year (Fiore 1987). The Chapman Site Profile assumes that the 

material was on site through April 30, 1949, which was the end of Electro Metallurgical’s reporting 

period regarding Chapman Valve uranium processing (discussed further below). 

Twenty-six tons of uranium rods were sent to the Chapman Valve Oak Street facility on January 9, 

1948 (Fiore, 1987). On January 15, 1948, Wolf wrote, “A survey of proposed uranium machining 

operation...” indicating that the facility had not yet started machining production quantities of 

uranium (Wolf, 01-21-48). In an April 28 to May 5, 1948, weekly report Wolf states, “Health and 

safety preparations at the Chapman Valve plant in Indian Orchard, Mass., for the proposed machining 

operation were investigated by the Radiation Survey and Safety Sections,” indicating the facility still 

had not begun machining as of May 5, 1948 (Wolf, 05-06-48). 

After the production period ended, Chapman Valve had over 27,000 pound of metal scrap, oxides, and 

sweepings, which were to be shipped off site (ORNL/RASA-92/1). A Crane Company letter noted 

that there was correspondence indicating that all radioactive residues and contaminated material had 

been shipped off of the site as of December, 1948 (the Crane Company purchased Chapman Valve in 

1959 and discontinued all manufacturing early in 1987). Another note indicates that the “27,000 

pounds of metal scrap, oxides, sweepings, etc., were shipped off site several months after the contract 

was complete.” Other documentation is unclear regarding whether another shipment of source and 

fissionable material would be made after January 25 (Morgan, 1949). An enclosure to Fiore and 
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ORNL state that Chapman Valve had in their possession over 27,000 pounds of metal scrap, oxides, 

sweeping, etc., for several months beyond completion of the contract (Fiore, 1987 and ORNL/RASA92/1). Both documents refer to a Chapman Valve letter dated November 8, 1948, that requested 

termination of AEC film badge services and indicated that all radioactive residues were surveyed by 

Brookhaven Medical Group and shipped off site in December, 1948. The Electro Metallurgical 

Division of U.C. & C. Corp. was contracted to process Chapman Valve material and scraps. About 

28,000 pounds of metal from Chapman are mentioned in the Electro Metallurgical weekly production 

report dated April 1 through April 30, 1949, indicating that the final shipment would have been no 

later than April 30, 1949 (Electro, 1949). Thus the Chapman Valve radiological operational period is 

assumed to have ended no later than April 30, 1949, with only residual radioactivity addressed after 

that date. 

Once the AEC operations were completed at Chapman, all associated equipment was removed and the 

area cleaned and surveyed (Chapman, 1996). As indicated in the ORNL July 1992 Chapman Valve 

radiological survey report (ORNL/RASA-92/1), the Chapman Valve Indian Orchard site became part 

of the Crane Company in 1959. The 1992 report indicates that at the time of the survey, Building 23 

had been vacant since the cessation of all operations at the former Chapman Valve site in 1987. For 

the purposes of this evaluation, the period of post-April 30, 1949 Chapman Valve operations, up to the 

commencement of remediation operations in 1994, is considered a residual radioactivity period. 

5.2 Radiological Exposure Sources from Chapman Valve Operations 

Records indicate that Chapman Valve, under contract with the Brookhaven Laboratory, machined 

uranium metal during the period January, 1948, through November, 1948, although machining of 

production quantities probably did not begin until May, 1948. As indicated in the Dvorchak affidavit, 

“During the course of operations uranium rods were brought to the facility by railroad car on a track 

which ran immediately adjacent to the building. The (uranium) rods were cut by a mechanical saw 

and then machined to the shape requested by the customer” (Dvorchak, 1987). 

Based on the reviews of the documentation for Chapman Valve (including data related to operations 

and associated radiological monitoring data), Chapman uranium operations were associated with the 

machining of natural uranium for BNL. The indication that only machining operations were 

performed is supported by the job title information in the dosimetry records provided for Chapman 

Valve (Musgrave, 1948; AEC 05-06-48). 

As part of the development of the Chapman Valve TBD, the Chapman Valve uranium internal 

exposure scenarios associated with operations were compared to similar operations at other sites (i.e., 

Y-12 and Simonds Saw and Steel). (Because film badge data are available for Chapman Valve 

workers, further evaluation of external exposures based on workplace data or comparisons to 

operations at other sites was not performed.) The Simonds Saw and Steel site was used for internal 

exposures comparison for Chapman radiological operations because of Simonds’ larger volume of 

uranium work, abundance of monitoring data, and the similarity of its source term and operations in 

1948. Simonds primarily performed rolling operations with natural uranium from 1948 through 1956; 

however, those operations did include grinding and forging processes. The Y-12 site was used for 

internal exposures comparison based on large-scale uranium machining operations in the same period 

as the Chapman Valve machining operations, although the source term for Y-12 machining operations 

was primarily depleted uranium. 
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Based on the review of operations-related documents, the source of internal radiation exposure at 

Chapman Valve was uranium dust produced from the manipulation of metals during machining and 

related processes. The source of external radiation was associated with working in close proximity to 

uranium metal and containers/drums of uranium wastes (turnings, shavings, contaminated waste 

materials, etc.). 

Chapman had set aside approximately one-third of Department No. 40 in Building 23 of the Chapman 

Plant Site, 203 Hampshire Street, Indian Orchard, Massachusetts, to engage in this program 

(Ungerland, 1987). Uranium rods were brought to the facility by railroad on a track immediately 

adjacent to the building. The uranium operations performed at Chapman resulted in airborne 

contamination in Building 23, as indicated by the bioassay and airborne radioactivity measurements 

during the 1948 operations, and by the surface contamination of the area reported by the 1992 

Building 23 residual contamination pre-remediation radiological survey (ORNL/RASA-92/1). As 

discussed in Section 7.4.1.5, the uranium was of natural enrichment. There was no indication that 

recycled uranium was processed at Chapman Valve (recycled uranium did not enter process streams 

until at least 1952). Available documentation indicates that Chapman Valve’s 1948-1949 uranium 

work for Bechtel National, Inc., (BNI) was confined to Building 23 and the adjacent railcar area. The 

restricted, uranium operations portion of Building 23 was separated from the remainder of the 

Building by a floor to ceiling wooden partition. Individuals were admitted to the restricted portion of 

this building/department by a guard (Chapman, 1996). A residual radioactivity period existed at 

Chapman Valve after the end of operations in April, 1949, until 1994 when remediation activities 

commenced under BNI management. 

Records mention a fire in the restricted area of the AEC project, which probably occurred in early 

June, 1948 (Fox, 1949). The exact nature of the fire and extent of the damage is unknown, although 

records indicate two people (guards) put out the fire and five people (foreman, captain of the guards, 

and three helpers) were involved in the cleanup. There is no indication that off-site firefighters were 

contacted to assist in containment of the fire. The involvement of uranium metal in the fire is 

suggested by a Chapman Valve letter dated January 19, 1949, that indicates urine samples were taken 

from the men who fought and put out the fire, and the men who were involved in the clean-up process. 

The monitoring data available from this incident are discussed further in Section 6.1. 

5.2.1 Alpha Particle Emissions 

Alpha particle emissions from the radioactive materials handled at the Chapman Valve facility 

presented the greatest potential for exposure through internal deposition via inhalation and ingestion 

(alpha particles do not present an external exposure hazard). The principal alpha-emitting radioactive 

material associated with Chapman Valve operations was natural uranium. Processed natural uranium 

consists of approximately equal activities of uranium-238 [4.20 MeV and 4.15 MeV alpha particles] 

and uranium-234 [4.77 MeV and 4.72 MeV alpha particles] (Radiological Health, 1970). There are 

smaller amounts of uranium-235 (approximately 1/20 of the activity levels of uranium-238 or 

uranium-234) with alpha particles of 4.40 MeV and 4.36 MeV. 
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5.2.2 Beta Radiation Fields 

Beta radiation was the dominant external source of radiation associated with activities involving 

contact with unshielded sources of uranium, such as the uranium machining processes at Chapman 

Valve. The dominant beta radiation from natural uranium is from the uranium-238 decay products. 

The most energetic of these beta particles is 2.29 MeV from protactinium-234m. The beta dose rate 

from the surface of a uranium slab is on the order of 230 millirad (mrad) per hour. 

5.2.3 Neutron Exposures

Neutron exposures are not evaluated for Chapman Valve because they are negligible for natural 

uranium metal-handling facilities (ORAUT-OTIB-0004). 

5.2.4 Photon Exposures 

The majority of photons from natural uranium metals are in the 30 to 250 keV energy range. In 

contrast, solid uranium objects provide considerable shielding of the lower-energy photons and 

“harden” the spectrum, causing the majority of photons emitted from a solid uranium object (e.g., a 

billet or rod) to have energies greater than 250 keV. While the solid uranium sources at this facility 

were likely to have a hardened photon spectrum, exposure to a thin layer of uranium on surfaces, 

whenever that occurred, would have resulted in a larger fraction of exposure to lower-energy photons, 

in the 30 to 250 keV range. This evaluation assumes that workers were exposed entirely to 

lower-energy photons, which is claimant favorable (ORAUT-TKBS-0033). 

6.0 Summary of Available Monitoring Data for the Proposed Class 

NIOSH has personal and area monitoring data in the NIOSH Site Research Database (SRDB) which 

have been used to estimate doses to individual employees in the proposed class. The results of NIOSH 

data reviews are provided in the following subsections. 

6.1 Chapman Valve Internal Monitoring Data 

As discussed in Section 5.2, the primary source of internal radiation exposure at Chapman Valve was 

uranium dust produced from the manipulation of metals during machining and related processes. 

Chapman Valve internal monitoring data are available to evaluate these potential exposures for the 

operation period (Urine, 1948). After the conclusion of uranium machining operations and clean-up 

in 1948, no additional bioassay data were collected (there would have been no regulatory reason to 

obtain further internal monitoring data from the point in time when uranium operations ceased up to 

the commencement of remediation activities, which occurred after the evaluation period of this 

report). 

NIOSH analyzed results from four sets of bioassay samples (urinalyses) during the development of 

the Chapman TBD dose reconstruction method. This included the seven bioassay samples taken on 

June 11, 1948, after (and in response to) the fire and samples collected on July 26-27, September 8-9, 

and October 7 of 1948 from 22, six, and five workers, respectively (ORAUT-TKBS-0033). The job 
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titles associated with the bioassay samples are listed in Table 5-1. There is no information in the 

sample report that indicates why the samples were taken. Further evaluation of this data is included in 

Sections 7.1 and 7.2 of this evaluation report. 

Table 5-1: Job Titles Associated with 1948 Chapman Valve Bioassay Samples

Asst. to Director of Research Heat Treater - Foreman 

Captain of Guards Helper 

Centerless Grinder Helper - Janitor 

Chief Electrician Helper - Weighing 

Chief Inspector Inspector 

Electrician Inspector - H. K. Ferguson Co. 

Engineer Machine Repair 

Foreman Master Mechanic 

Foreman, Steam Fitting & Plumbing Maintenance Milling Machine Operator 

Foreman - Substitute Personnel Manager 

Gen. Superintendent, Machine Shops & Maintenance Steamfitter 

Guard Turret Lathe Operator 

For the post-April 30, 1949, residual contamination period, there is an indication that radiological 

surveys were performed: (1) in 1949, after cleaning/decontamination activities (post-operation) 

(Chapman, 1996); (2) in 1987, after all operations were discontinued at the site (Sedelow, 1987b); and 

(3) in 1991, as referred to in a letter discussing a radiological survey (Williams, 1991). However, no 

survey data are available for any of these surveys. Internal exposure assessment methods have been 

developed in the Chapman Valve TBD (ORAUT-TKBS-0033) based on the available radiological 

survey data from a 1992 ORNL radiological survey of Building 23 (ORNL/RASA-92/1). 

6.2 Chapman Valve External Monitoring Data 

Chapman Valve reported the following ancillary information regarding film badge availability and use 

during the uranium machining operations period (Musgrave, 1948): 

• February 2, 1948: Received 50 (brass) badges from the University of Rochester. 

• February 9, 1948: Received duplicate shipment (with identical numbers) noted to be the pin-type 

dosimeters. 

• April 28, 1948: Requested 100 badges and subsequently received 100 stainless steel snap-on 

badges from the University of Rochester. 

• May 10, 1948: Returned the 50 used brass pin-type dosimeters and 50 used stainless steel snap-on 

badges to the University of Rochester. 

• May 18, 1948: Received 100 stainless steel snap-on badges and noted that Chapman Valve would 

like to continue this badge type. 
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• May 19, 1948: Sent 50 brass pin-type and 50 stainless steel snap-on badges to AEC in New York 

per AEC request. 

Less than 50 film badge results are included in each reporting period, most likely indicating that only 

some of the workers entered the AEC work are in a given week. A note at the bottom of the May 

reports states “Eastman Film,” but does not mention the type of film (ORAUT-TKBS-0033). 

In the Chapman Valve records, exposure for both beta and gamma were reported in “mr” in 1948. 

There are 81 individual film badge assignments and 1365 external dosimetry results for Chapman 

Valve employees reported for the weeks from May 3, 1948, through November 1, 1948. The 

reporting limit, as indicated in the film badge records, was 50 mR for beta and for gamma radiation. 

These data were reviewed in the development of the Chapman Valve TBD to identify the median and 

maximum reported results for each week (ORAUT-TKBS-0033). 

As indicated in Section 5.1, production level machining activities were most likely performed from 

May, 1948, through November, 1948. However, the first reported shipment of uranium in the form of 

rods ready to be machined was on January 9, 1948. Uranium in the form of floor sweepings, turnings, 

and shavings were on site after the completion of machining operations, possibly as late as April 30, 

1949. These pre- and post-operational periods, for which monitoring data does not exist, have been 

treated for the purposes of dose reconstruction as operationally-unmonitored periods (ORAUT-TKBS0033). As discussed in Section 7.3.1, the available operational period monitoring data have been used 

to establish bounding exposure scenarios for the unmonitored period for the dose reconstructions 

completed to date. 

NIOSH has not found any information regarding AEC-required physical examinations for Chapman 

Valve employees. The AEC usually, but not always, required “pre-employment” and periodic 

medical examinations of workers involved in the larger uranium-processing programs. The term 

“pre-employment,” as used here, means prior to performing AEC-contracted radiological work. The 

typical AEC medical program included a preliminary and annual chest X-ray examination. NIOSH 

has data to characterize the radiological exposures associated with such examinations (ORAUTOTIB-0006). 

For the post-April 30, 1949, residual contamination period, there is an indication that radiological 

surveys were performed: (1) in 1949, after cleaning/decontamination activities (post-operation) 

(Chapman, 1996); (2) in 1987, after all operations were discontinued at the site (Sedelow, 1987b); and 

(3) in 1991, as referred to in a letter discussing a radiological survey (Williams, 1991). However, no 

survey data are available for any of these surveys. External exposure assessment methods have been 

developed in the Chapman Valve TBD (ORAUT-TKBS-0033) based on the available radiological 

survey data from a 1992 ORNL radiological survey of Building 23 (ORNL/RASA-92/1). 

6.3 Chapman Valve Air Sampling Data 

The AEC provided air sampling analyses for samples collected at Chapman Valve on May 4, 1948, 

and May 24, 1948 (AEC, 05-06-48; AEC, 06-01-48). The May 4, 1948, sample results are 

measurements of the effluent from a furnace outlet on the roof of Building 23. The May 24, 1948, 

results are 10-minute samples listed as “Inspection Bench, Packing Bench, Work Bench, Wash Room, 
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and Lunch Room.” These samples are not directly used in determining worker intakes in the dose 

reconstructions completed to date because it is not clear how these samples relate to worker activities. 

As an estimate, however, an inhalation intake was calculated by assuming that the maximum result 

reported (29.1 dpm alpha/m3

 measured at the workbench) was the concentration for the entire work 

year. Upward adjustment of this number to account for the increased workload in the summer 

months, as well as accounting for ingestion, results in an intake value that is consistent with the intake 

value determined from bioassay results. 

NIOSH has identified no air sample data from its reviews of the available data for the post-April 30, 

1949, residual radioactivity period. 

7.0 Feasibility of Dose Reconstruction for the Proposed Class 

The feasibility determination for the proposed class of employees covered by this evaluation report is 

governed by EEOICPA and 42 CFR § 83.13(c)(1). Under this Act and rule, NIOSH must establish 

whether or not it has access to sufficient information to either, estimate the maximum radiation dose 

for every type of cancer for which radiation doses are reconstructed that could have been incurred 

under plausible circumstances by any member of the class, or to estimate the radiation doses to 

members of the class more precisely than a maximum dose estimate. If NIOSH has access to 

sufficient information for either case, then it would be determined that it was feasible to conduct dose 

reconstructions. 

In making determinations of feasibility, NIOSH begins by evaluating whether current or completed 

NIOSH dose reconstructions demonstrate the feasibility of estimating with sufficient accuracy the 

potential radiation exposures of the class (identified in Section 7.5 of this report). If not, NIOSH 

systematically evaluates the sufficiency of different types of monitoring data, process and source or 

source term data, which together or individually might assure NIOSH can estimate either the 

maximum doses members of the class might have incurred, or more precise quantities that reflect the 

variability of exposures experienced by groups or individual members of the class. This approach is 

specified in the SEC Petition Evaluation Internal Procedures (OCAS-PR-004) available at 

www.cdc.gov/niosh/ocas. 

The evaluation that follows examines separately the availability of information necessary for 

reconstructing internal and external radiation doses of members of the proposed class. 

7.1 Sufficiency of Chapman Valve Data 

Chapman Valve machined natural uranium under an Atomic Energy Commission contract in 1948. 

As discussed in Section 5.2 of this report, the potential for radiological exposures associated with the 

machining of uranium rods, and from containers/drums of uranium wastes (turnings, shavings, 

contaminated waste materials, etc.), is assumed to have existed at Chapman Valve from January 1, 

1948, until April 30, 1949. During the main machining period from May to November, 1948, workers 

were monitored for occupational radiation exposure and monitoring records are available. All other 

periods outside of the main machining period have been considered unmonitored periods (either 
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unmonitored operational periods or residual radiation periods) for the purposes of dose 

reconstructions conducted to date. 

The AEC (Wolf, 1947) planned the initial health and safety controls and monitoring at Chapman 

Valve: “On November 24 [1947], a conference was held with Chapman Valve and Ferguson 

personnel as a result of which a complete set of health and safety recommendations were made a few 

days later in writing.” To monitor external exposure, 100 film badges were provided each week 

(Musgrave, 1948). The existence of an AEC health and safety program at the Chapman Valve facility 

was also documented in a letter from Crane (Crane, 1987; page 8). 

Area access controls were in place at Chapman Valve and were applicable to all job categories. These 

controls were in place for security, contamination, and radiation exposure control purposes 

(Ungerland, 1987). Although access control records and AEC reports provide evidence of a radiation 

control program, no formal documentation of the program was found. Because bioassay data and film 

badge data were used to estimate internal and external doses at Chapman Valve during the AEC 

operations (ORAUT-TKBS-0033), it was not necessary to estimate the number of workdays or workhours for the January 1, 1948, through April 30, 1949, period. For the purpose of estimating postoperational/residual radioactivity exposures (for the post-April 30, 1949, period), it was assumed that 

workers worked 8 hours per day, 50 weeks per year, for an annual total of 2000 hours. 

The following subsections evaluate the data in terms of sufficiency for establishing bounding 

exposure scenarios for the proposed class. The review focuses on the available personnel monitoring 

data used in the development of the Chapman Valve TBD and this evaluation report. 

7.1.1 Pedigree of Data 

7.1.1.1 External Data Review 

For this evaluation report, NIOSH compared the three files containing individual external monitoring 

data that were used in the development of the Chapman TBD (SRDB Ref IDs: 10749, 14131, and 

16436). Based on this review, NIOSH concluded that file 16436 appeared to be a copy of an original 

handwritten documentation of the individual monitoring data for the operational period from May to 

November, 1948. The file contains weekly external monitoring data listed by badge number and/or 

individual name/job title. In addition, the file contains some reports of individual hours spent in the 

restricted area, although reports were not found for all days for which external monitoring was 

performed. 

There is also a ‘cleaned-up’ (mostly typed) version of the handwritten film badge results in files 

10749 and 14131. NIOSH has determined that files 10749 and 14131 contain duplicate data (i.e., the 

same document scanned at different levels of visual quality). The ‘cleaned-up’ version was verified to 

contain the same data as the handwritten version with the following differences: (1) the ‘cleaned-up’ 

version only contains the individual monitoring data, not the work-hour information; and (2) the 

‘cleaned-up’ version eliminates lines that contain no data or where there is an indication that badges 

were not used for a particular period. 

These files document that a total of 81 different individuals were assigned badges at Chapman Valve 

and includes 27 weeks of monitoring data. Badges were exchanged on a weekly basis. NIOSH 
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compared the data transcriptions from the original handwritten files to the ‘cleaned-up’ versions and 

found them to be accurate. The only differences in these data are that un-quantified doses, indicated 

with an ‘X’ (which NIOSH interprets to be a dose that was less than the minimum detectable dose), 

were not always transcribed into the typed versions (they were left blank). The maximum weekly 

doses documented were 650 mR non-penetrating and 110 mR penetrating for the May – November 

1948 period. The median beta result for May, 1948, was (115 mR) and the reporting limit specified 

on the Chapman Valve reports for gamma (50mR) were used to estimate the exposure for weeks when 

film badges were not in use or for weeks when the data were blank. 

For the post-April 30, 1949, residual radioactivity period, NIOSH reviewed the file containing the 

radiological survey data used in the development of the residual radioactivity portion of the Chapman 

TBD (ORNL/RASA-92/1). The source documentation associated with this survey was not available; 

therefore, an internal comparison of this data was not possible. 

7.1.1.2 Internal Data Review

NIOSH reviewed for this evaluation the file containing individual internal monitoring data used in the 

development of the Chapman TBD (SRDB Ref ID: 6235). An internal comparison of the data after 

June, 1948, was not possible because no other source bioassay files were available for Chapman 

Valve. 

As part of the data sufficiency review, NIOSH also considered the urine data for individuals involved 

in the fire of June, 1948 (SRDB Ref ID: 12730), for which bioassay results had redacted names. 

There are seven samples - from two workers involved in putting out the fire, and from five workers 

involved in clean-up. These results are the same as the June 11, 1948 results in an un-redacted file 

containing fire follow-up bioassay data (SRDB Ref ID: 6325). These results thus comprise a single 

source of data; therefore, an internal data comparison was not possible. 

7.1.2 Credibility and Consistency of Data 

7.1.2.1 External Data Review 

The three files discussed in Section 7.1.1.1 (SRDB Ref IDs: 10749, 14131, and 16436) were reviewed 

to evaluate data credibility and consistency. Other than the discrepancies described in Section 7.1.1.1, 

no other issues were identified during the reviews and comparisons performed by NIOSH for this 

evaluation report. All three files contain essentially the same data/pages, with the smallest file a 

refinement of the previous two. File number 16436 is the most comprehensive, 14131 is the initial 

refinement, and 10749 is a re-scanned copy of 14131. File number 16436 has 1778 entries in the Last 

Name column and 1365 values in the exposure column (including lines marked with “none,” 

indicating that a badge was not worn). File number 14131 has 1404 entries in the Last Name column 

and 781 values in the exposure column. The files were cross-checked in a variety of ways. The 

discrepancies in the data comparison also reflect the difference in source document quality. Data 

transfers from 16436 to 10749 were compared and are accurate. The only discrepancies noted were 

the transfer of doses of < 50 mR which were sometimes left as no entries. 

Based on the review of the external dosimetry files (Section 7.1.1.1), all job titles listed in the SEC 

petition are represented in external monitoring data, with the exceptions of Assembler, 
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Decontamination Worker, and Firefighter. The source of the job titles listed in the petition is not 

known and cannot be ruled out as slang terms or terms that represented an actual work activity. Based 

on a review of the petition documentation, the job title “assembler” appears as a title for one of the 

(deceased) former energy employees represented in the petition. As indicated in the former energy 

employee’s individual claim file, the title listed is “assembling,” which appears to a description of 

work instead of a job title. This former energy employee also had the title of “valve machinist” listed 

in the petition. Based on this review, machinists would appear to be a reasonable representation for 

“assembling” or “assembler” work, as evaluated in this report. Decontamination work could have 

been performed by any of the job titles listed in the petition but was likely performed by the helpers 

and is not expected to be a primary job title during the Chapman operational years (i.e., it is more a 

description of the work performed). The potential for the existence of this job title, for radiological 

decontamination work, is more likely in the post-April 30, 1949, residual contamination period 

evaluated in this report. This job title is most likely to apply to the 1994-1995 remediation period, 

which is not being evaluated in this report. It does not appear that a job title of firefighter was 

associated with the AEC uranium work; workers who put out the June, 1948, fire were either guards, 

helpers, or a foreman. 

The Chapman data have been reviewed to identify the maximum results for each week. The median 

beta result for May, 1948, (115 mR) and the reporting limit specified on the Chapman Valve reports 

for gamma (50mR) were used to estimate the exposure for weeks with no film badge results. 

7.1.2.2 Internal Data Review 

Chapman Valve uranium urinalysis data (Urine 1948) consist of 40 uranium urinalysis results from 37 

workers (three workers have two results each). Bioassay results are available for seventeen of the 

twenty-six job titles listed in the petition are covered by the bioassay samples. 

Simonds Saw and Steel was a larger uranium-handling AWE operating in 1948 with comparable 

activities involving rolling, grinding, and forging. AEC-contracted Y-12 operations during the period 

involved even larger amounts of uranium with comparable activities that included machining. 

Bioassay data from these two sites were compared to the Chapman Valve bioassay data. No Y-12 

bioassay data were available for 1948; the earliest readily-available data was for 1952. To expedite 

the comparison, the Y-12 data from the month with the largest geometric mean was selected. (Records 

indicate that although there are Y-12 uranium urinalyses for 1950 and 1951, results are lower than for 

1952; operations might have been curtailed, and there were concerns about the particular analytical 

methods used at Y-12.) Y-12 data was reported in terms of daily uranium activity in urine, so results 

were converted to ug/L, assuming a uranium specific activity of 0.683 pCi/ug, and an excretion of 1.4 

liters per day. 

The amount of uranium handled by Simonds Saw and Steel in the late 1940s was likely to be at least 

10 times the amount handled by Chapman Valve. Sometime in 1949, Simonds ramped up to process 

about 150,000 lbs. of uranium per month, which is more than three times the amount of uranium 

processed by Chapman between January and July of 1948. It is suspected that Chapman processed 

less than 300,000 lbs. total and might have processed no more than 141,200 lbs. The throughput of 

uranium at Y-12 is likely to also have been larger than at Chapman. The information from these 

comparisons is included in Table 7-1. 
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Although seven bioassays were collected as a result of the fire at Chapman, fires were not rare at 

uranium processing facilities during the early years; co-worker data from all sites would include 

bioassay related to incidents as well as normal operations. The geometric means and GSDs were 

based on ranking and fitting the natural log of the bioassay results to a line, as is done for the 

associated co-worker studies. It should also be noted that for Chapman, when all results were below 

the detection threshold in a given sampling period, the detection threshold was used for fitting the 

intakes. 

Table 7-1: Comparison of Bioassay Data for Y-12, Simonds Saw and Steel, and Chapman Valve 

Comparison Topic Chapman Simonds Simonds Y-12 

Period of monitoring 

considered 

1948 1948-1952 1948 only 1952 (April) 

Number of uranium 

urinalyses 

40 645 67 - 

Geometric mean 

(ug/L) 

7 8 17 12 

GSD 2.34 3.06 2.08 2.91 

95th percentile (ug/L) 30 51 58 70 

Percentage of 

bioassay results 

≤40ug/L 

95% 96% 91% - 

Range of geometric 

means for each 

sampling period 

(ug/L) 

7 to 17 1 to 27 11 to 22 - 

Percentage of results 

>40 ug/L 

5% 4% 9% - 

The Simonds and Y-12 uranium urinalyses provide comparable datasets of results for uranium metal 

handling activities. The Chapman Valve bioassay results appear to be consistent with an operation 

that worked with less uranium for a shorter duration than Simonds Saw and Steel and Y-12. 

NIOSH determined the number of Chapman Valve personnel who were monitored for both internal 

and external radiation exposures during the operational period. All but two individuals with urinalysis 

results had external dose data. Therefore, 46 of the individuals who had dosimeters had no records of 

uranium urinalysis. 

7.1.3 Data Sufficiency Conclusions 

Individual film badge results are available to determine doses. The reporting limit for beta and 

gamma was 50 mR. The TBD provides claimant-favorable assumptions that can be used to estimate 

external doses for those Chapman Valve claims. Some job titles are included with the external dose 

records; however, job titles do not require specific consideration for most dose reconstructions. The 

uranium bioassay data have been compared with similar but larger operations and, as discussed in 

Section 7.1.2.2, the data is comparable. A review of bioassay results at both sites shows the 

following: the maximum result at Chapman was 0.08 mg/L. Only 5 of the 645 results at Simonds 

exceeded 0.08 mg/L. The maximum result after June, 1948, at Chapman did not exceed 0.04 mg/L. 
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The Chapman Valve bioassay results are consistent with an operation that worked with less uranium 

(than Simonds Saw and Steel or Y-12) for a shorter duration. 

• External dosimetry data: Film badges were assigned to 81 individuals and 1365 external dosimetry 

results for Chapman Valve were reported for the weeks beginning May 3, 1948, through 

November 1, 1948. This period is believed to have been the duration of major uranium operations 

for the site. Records indicate that personnel who entered the AEC-work area were required to 

wear dosimeters. Documentation indicates that brass pin-type and stainless steel snap-on badges 

were used; these were film badges, although the film type is not specified. The film badges were 

sent to the University of Rochester for processing. The reporting limit was 50 mR for beta and for 

gamma radiation. It is not possible to associate results with specific individuals in most cases 

because of poor copies or censored identifiers, but the data have been reviewed to identify the 

maximum results for each week. The median beta result for May, 1948, (115 mR) and the 

reporting limit specified on the Chapman Valve reports for gamma (50mR) were used to estimate 

the exposure for weeks with no reported film badge results (ORAUT-TKBS-0033).

• Internal dosimetry data: Standard photofluorometric methods were used. Typewritten reports are 

included in the files, and correspondence regarding the 1948 fire indicates that the AEC 

maintained the bioassay data. Detection thresholds likely ranged between 5 and 10 ug of uranium 

per liter of urine (Wilson, 1958). The uranium photofluorometric urinalysis detection threshold at 

Chapman Valve is assumed to be 10 ug/L. The data appear to be representative of the workers 

and the work, and are consistent with sites involved in similar activities, such as Y-12 and 

Simonds Saw and Steel (given the difference in uranium throughput). The urine samples were 

collected after a fire in mid-1948 as well as during the operations thereafter. Results of four sets of 

worker bioassay data collected during 1948 were used to develop the Chapman co-worker intakes 

for dose reconstruction. The data are consistent with analyses of bioassay and air sampling data 

for similar uranium operations during this period.

NIOSH has investigated the pedigree, credibility, and consistency of the external and internal 

monitoring data for Chapman Valve. NIOSH has not found any evidence of censoring of data or data 

manipulation that would cast doubt on the integrity of the data for use in dose reconstruction or in the 

generation of co-worker dose distributions. It is reasonable to conclude that a credible and reputable 

source was used to analyze the internal and external monitoring samples/dosimeters. The University 

of Rochester School of Medicine and Dentistry was under contract with AEC’s NYOO to perform 

sample/dosimeter analysis. The University of Rochester performed the bioassay analysis of the 1948 

fire urine samples and the dosimeter analysis for all Chapman Valve film badges (Fox, 1949). No 

clear evidence identifies the organization that analyzed the remaining bioassay data. Based on the 

analysis results for other sites during this time period (e.g., Simonds Saw and Steel), the likely 

analyzing organization was either the AEC Health and Safety Division (predecessor of HASL) or the 

University of Rochester. 
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7.2 Internal Radiation Doses at Chapman Valve 

For the period January 1, 1948, through April 30, 1949, radioactive materials could have become 

airborne as a result of activities and practices associated with the machining of uranium, including the 

1948 uranium fire. Internal radiation exposure during this operational period was from natural 

uranium dust produced from the manipulation of oxidized metals during machining and related 

processes. In addition, internal exposures could have occurred for individuals exposed during the 

documented fire. For unmonitored workers or unmonitored periods, the TBD analyzes the bioassay 

results to provide estimates of co-workers’ uranium intakes (ORAUT-TKBS-0033). Furthermore, 

intakes of radioactive material was possible after operations were completed (from May 1, 1949 

through December 31, 1949, and from January 1, 1991 through December 31, 1993) because of 

exposures associated with the remaining residual radioactive material (the period from January 1, 

1950, through December 31, 1990, falls outside proposed class). The only source term that existed at 

Chapman for all periods evaluated in this report was associated with natural uranium. Recycled 

uranium did not enter process streams until 1952, so no recycled uranium would have been processed 

at Chapman during the 1948 to 1949 operational period (ORAUT-TKBS-0033). 

7.2.1 Process-related Internal Doses at Chapman Valve 

The following subsections summarize the extent and limitations of information available for 

reconstructing the process-related internal doses of members of the proposed class. 

7.2.1.1 Urinalysis Information and Available Data 

Individual uranium urinalysis data are available for some Chapman Valve workers. Urinalysis results 

less than 0.01 mg/L were reported as zero. As indicated in the uranium results (author unknown; 

Urine, 1948), “...the uranium content of those samples listed as containing less than 0.01 mg U/l is 

below the limit for reliable determination by the photofluorometric method” and were, therefore, 

reported as zero. The urinalyses results in this record range from <0.01 to 0.08 mg/L. 

Forty Chapman bioassay results were available for samples collected on June 11, July 26-27, 

September 8-9, and October 7, 1948, from 7, 22, 6, and 5 workers, respectively. The median and 84th

percentiles were estimated for each set. The daily uranium excretion in urine was calculated by 

multiplying the results in mg/L by the specific activity of natural uranium (682.96 pCi/mg) and by 

reference man’s daily urine output (1.4 L/day) (ICRP 23). Table 7-1 shows the bioassay results used 

in the intake analyses. The Table 7-2 bioassay values were used to estimate median and 84th 

percentile inhalation intake regimes based on an acute exposure in June, 1948, and a chronic exposure 

from January 1, 1948, to April 30, 1949. When intakes are estimated from bioassay data, the mode of 

intake is usually assumed to be inhalation unless there is information indicating that other intake 

modes are more likely. When using bioassay data, the inhalation intake model assumes that some of 

the intake behaves as ingested material. In general, intake results from bioassay will be larger when 

an inhalation rather than an ingestion intake is assumed. 
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Table 7-2: Bioassay Results from Co-worker Data

Bioassay Date Median Bioassay 

(pCi/day) 

84th Bioassay 

 (pCi/day) 

6/11/1948a 16.7 54.6 

7/27/1948b 7.43 11.3 

9/8/1948c 9.56 9.56 

10/7/1948d 9.56 9.56 

Source: Urine, 1948 

Notes: 

a. The seven results were log-transformed and fit to a line, from which a geometric mean and GSD were calculated. 

b. The 22 results were log-transformed and fit to a line, from which a geometric mean and GSD were calculated. 

c. Five of the six results were reported as 0.01 mg/L and one was reported as <0.01 mg/L. The geometric mean and the 

84th percentile were assumed to be 0.01 mg/L. 

d. Two of the five results were reported as 0.01 mg/L and three were reported as <0.01 mg/L. The geometric mean and the 

84th percentile were assumed to be 0.01 mg/L. 

There were uranium intakes resulting from a fire in June, 1948 (Fox, 1949). Although the date of the 

fire is unknown, it was assumed to have occurred as early as June 1, 1948. The co-worker data fit the 

assumed intake regimes better when it was assumed that the intake from the fire and the clean-up 

occurred closer to the date of the bioassay. The bioassay data support both the chronic and acute 

intake regimes for all the scenarios used to fit the data only when the acute intake from the fire is 

assumed to occur during the period June 7 to June 10, 1948, inclusive. The assumption that the intake 

from the fire occurred on June 10, 1948, resulted in the largest total intake. The intake resulting from 

the fire and clean-up might have occurred over several days, but it was assumed to be an acute intake 

when fitting the data in order to simplify assumptions. 

The combinations of uranium machining and fire intakes were calculated with IMBA ExpertTM 

OCAS-Edition, Version 3.2.20, assuming an absolute uniform error of one and a normal error 

distribution. To calculate the level of chronic intake for workers who might not have been exposed to 

the fire, the June 11, 1948, bioassay results were excluded. The geometric standard deviations were 

calculated by dividing the intake from the 84th regime by the intake from median regime. Table 7-3 

shows the inhalation intakes from the analyses of the Chapman uranium urinalysis data. 
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Table 7-3: Inhalation Intakes Based on Co-worker Data 

Scenarioa Absorption 

Type 

Chronic Intake 1/1/1948 

to 4/30/1949 

(pCi/calendar day) 

Acute Intakea

(pCi) 

6/10/1948 

Total Intake 

during AEC 

work (pCi) 

Geometric 

Standard 

Deviations 

(intake) 

Uranium 

machining and fire M 1.50 E+2 3.69 E+2 7.29 E+4 1.14 

Uranium 

machining and fire S 4.45 E+3 1.28 E+4 2.17 E+6 1.13 

Uranium 

machining M 1.50 E+2 - 7.29 E+4 1.14 

Uranium 

machining S 4.48 E+3 - 2.17 E+6 1.14 

Source: ORAUT-TKBS-0033 

Note a: The acute intakes are associated with geometric standard deviations of about five. 

To estimate the total uncertainty in organ dose, the geometric standard deviation for each intake 

regime in Table 7-3 is combined with the assumed geometric standard deviation of three for the 

metabolic model (as presented in Section 7.2.1.2). 

Intake Assumptions

Human and animal studies have indicated that oxides of uranium can be very insoluble (ICRP, 1995), 

indicating absorption type S (0.1% and 99.9% with clearance half-times on the order of 10 minutes 

and 7000 days, respectively). Other in vitro dissolution studies of compounds found at uranium 

facilities have shown that oxides of uranium exhibit moderate solubility (ORAUT-TKBS-0033), 

suggesting absorption type M (10% and 90% with clearance half-times on the order of 10 minutes and 

140 days, respectively). In vitro dissolution tests on oxides produced from uranium metal during 

depleted uranium armor penetrating tests have indicated multi-component dissolution rates, with 25% 

of uranium dissolving with a half-time of less than or equal to 0.14 days and 75% dissolving with a 

half-time of 180 days. Because there was no specific information on the solubility of aerosols 

produced during Chapman operations, this analysis assumed that both types M and S were available. 

The selection of absorption type for a dose reconstruction is based on the organ of interest and 

selected to ensure claimant-favorability. For dose calculations, uranium intakes are assumed to be U234. 

The assumed operational exposure period ran from January 1, 1948, to April 30, 1949, which this 

evaluation assumes to be the natural uranium intake period. A uranium fire is assumed to have 

occurred sometime between June 1 and June 11, 1948. When analyzing individual bioassay data, the 

intake from the fire can be assumed to be acute and to have occurred on June 1, 1948, if no other 

information is available. 
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7.2.1.2 Unmonitored Workers – Application of Co-Worker Data for Internal Dose Reconstruction

The uranium urinalysis data from Chapman Valve were compared with data from a similar period 

(November 1-15, 1948) at Simonds Saw and Steel. The Simonds site was used for comparison 

because of its larger volume of uranium work, abundance of monitoring data, and the similarity of its 

source term and operations in 1948. The reported air concentrations associated with Simonds’ 

uranium operations appear to be much higher than the few air concentrations measured at Chapman. 

Simonds’ bioassay data for 1948 ranges from 0.00 ug/L to 0.09 ug/L for 67 samples, with only two 

samples greater than 80 ug/L. Based on this comparison, the bioassay results from Chapman Valve 

appear to be of a similar magnitude and distribution. The co-worker data set developed for Chapman 

Valve, using Chapman Valve and similar site data, is presented in Table 7-4. 

For unmonitored workers or unmonitored periods, Table 7-4 lists inhalation intake assumptions for 

natural uranium. Chronic intakes are given in units of pCi/d and acute intakes are given in pCi. Four 

different intake scenarios are listed. The first two scenarios account for exposure to the uranium fire 

in June. The last two scenarios can be used when an individual had no exposure to the fire, or to 

supplement intakes for workers whose bioassays are only associated with the fire. The dose 

distribution is assumed to be lognormal. Geometric standard deviations are listed in the table. 

Table 7-4: Inhalation Intake Summary for Operational Period 

Scenariosa Start End Intake 

Type 

Absorption 

Type 

Intake (pCi/day 

or pCi) 

Geometric 

Standard 

Deviation 

Fire plus workplace 

exposure 

1/1/1948 

6/10/1948 

4/30/1949 Chronic 

Acute 

M 

M 

1.50 E+2 

3.69 E+2 

3.02 

3.02 

Fire plus workplace 

exposure 

1/4/1948 

6/10/1948 

4/30/1949 Chronic 

Acute 

S 

S 

4.45 E+3 

1.29 E+4 

3.02 

3.02 

Workplace exposure 1/4/1948 4/30/1949 Chronic M 1.50 E+2 3.02 

Workplace exposure 1/4/1948 4/30/1949 Chronic S 4.48 E+3 3.02 

Source: ORAUT-TKBS-0033 

Note a: Only one of the four scenarios from the table is to be used to calculate an organ dose. A worker can qualify for 

only one of the scenarios. 

7.2.2 Ambient Environmental and Residual Radioactivity Internal Radiation Doses 

Further evaluation regarding the ambient environmental internal radiation doses for the period from 

January 1, 1948, through April 30, 1949, is not necessary because these doses are accounted for in the 

process-related internal dose evaluation. 

In the residual radioactivity years, data from a survey report in August, 1992 (ORNL/RASA-92/1), 

under the Formerly Utilized Sites Remedial Action Program (FUSRAP) were used to calculate 

intakes. The radiation levels reported at various facility locations are summarized in ORAUT-TKBS0033. Table 7-5 summarizes the annual internal exposures due to residual radiation for the period of 

May 1, 1949, to December 31, 1993. 
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Table 7-5: Annual Internal Exposure to Residual Radioactivity 

Internal Start End Exposure Absorption 

Type 

Intake 

(pCi/d) 

IREP Distribution 

Uranium 05-01-49 12-31-93 Inhalation M, S 8.58E-01 Lognormal GSD 3 

05-01-49 12-31-93 Ingestion (a) 1.79E-02 Lognormal GSD 3 

Note (a): Choose same f1 value as used for inhalation per OCAS-PR-004. 

7.2.3 Internal Dose Reconstruction Feasibility Conclusion 

Because both the Chapman bioassay data and the process knowledge of site support activities are 

limited, the Chapman Valve TBD (ORAUT-TKBS-0033) also considered information from sites with 

similar operations. Process information and levels of radioactivity encountered during this uraniummetal work are available for these similar sites. The Chapman Valve bioassay data, combined with 

contract information and uranium metal-handling process knowledge at other sites, are sufficient to 

either: (1) estimate the maximum internal radiation dose for every type of cancer for which radiation 

doses are reconstructed that could have been incurred under plausible circumstances by any member 

of the class; or (2) estimate the internal radiation doses to members of the class more precisely than a 

maximum dose estimate. 

7.3 External Radiation Doses at Chapman Valve 

The principal source of external radiation doses for members of the proposed class was natural 

uranium and its short-lived progeny in the form of metal rods. In 1948, Chapman Valve began 

machining uranium rods for Brookhaven National Laboratory and continued through April 30, 1949. 

This analysis assumes that the residual radioactivity period extended from May 1, 1949, through 

December 31, 1993. 

7.3.1 Process-related External Radiation Doses at Chapman Valve 

The following subsections summarize the extent and limitations of information available for 

reconstructing the process-related external doses of members of the proposed class. 

7.3.1.1 Individual Dosimetry Data

For the weeks beginning May 3, 1948, through November 1, 1948, Chapman Valve film badge results 

are available for 81 individuals. When available, individual dosimetry data for the operational period 

will be used to estimate the external radiation doses for members of the class more precisely than a 

maximum dose estimate. In the absence of individual data for members of the class, the co-worker 

approach in Section 7.3.1.2 will be used. 

Exposures reported for the weeks beginning October 11, 18, and 25 are questionable because the 

values on the data sheet appear to indicate that no results were reported, but a notation indicates that 

results were all less than 50 mR. This apparent discrepancy may be due to the practice of expediting 

data entry by marking multiple results that were “less than” with an X. The discrepancy was 

accounted for by using the median of the maximum reported beta result for May (115 mR) and the 
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reporting limit specified on the Chapman Valve reports for gamma (50mR) (which was maximizing 

for most weeks of exposure) to account for exposure during the weeks of no reported dose above the 

reporting threshold of 50 mR (ORAUT-TKBS-0033). 

7.3.1.2 Unmonitored Workers – Application of Co-Worker Data for External Dose Reconstruction

The analysis of the May to November, 1948, external monitoring data for the operational period is 

discussed in detail in the Chapman TBD (ORAUT-TKBS-0033). The median beta result for May 

(115 mR) and the reporting limit specified on the Chapman Valve reports for gamma (50mR) were 

used to estimate the exposure for other weeks when no film badge results were reported. Exposures 

during unmonitored weeks were likely to be lower because the majority of processing occurred 

between May and November, 1948; therefore, these estimates provide a bounding exposure scenario 

for the period from January to April, 1948, and from December, 1948, to April, 1949. The results of 

this analysis are presented in Table 7-6. 

Table 7-6: External Exposure Summary for Operational Period 

Exposure 

Category 

Exposure 

Type 

Exposure 

or Dose 

Rate 

Basis Year Annual 

Exposure 

IREP 

Distribution 

Penetrating 4/30/1949 Maximum 

film badge 

results 

1948 

1949 

2.830 R 

0.850 R Constant 

Overestimate 

of External 

Dose 

Nonpenetrating 4/30/1949 Chronic 

Acute 

1948 

1949 

9.110 R 

1.955 R Constant 

Source: ORAUT-TKBS-0033 

7.3.2 Ambient Environmental and Residual Radioactivity External Radiation Doses 

Further evaluation regarding the ambient environmental external radiation doses for the period from 

January 1, 1948, through April 30, 1949, is not necessary because these doses are accounted for in the 

process related external dose evaluation. 

The estimated annual external exposures to residual radioactivity from AEC operations at Chapman 

Valve, listed in Table 7-7, were calculated by assuming that workers were exposed for 2,000 hours per 

year. In the residual radioactivity years, data from a survey report in August, 1992 (ORNL/RASA92/1), under the Formerly Utilized Sites Remedial Action Program (FUSRAP), were used to calculate 

intakes. To estimate the penetrating dose, it was assumed that the largest average result, 13 uR/hr, 

was the median; and the largest result, 32 uR/hr, was at the 95th percentile. An associated GSD of 

1.72 was calculated. The annual penetrating dose estimate is listed in Table 7-7. 

In the 1992 survey, a pancake Geiger-Mueller (GM) probe measured count rates and these rates were 

converted to mrad/h of beta/gamma. The MDA was reported as 0.01 mrad/hr. Such a probe is also 

sensitive to alpha radiation, which might have resulted in an over-response if a cover or distance from 

a surface being measured was not maintained to eliminate the alpha response. ORNL (ORNL/RASA92/1, Figure 7) reported a range of dose rates for each grid block surveyed. The maximum dose rates 
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in the range were used to determine a geometric mean, which was assumed to equal a median nonpenetrating dose rate, 0.12 mrad/h. The GSD was calculated to be 2.9. The annual non-penetrating 

dose is listed in Table 7-7. 

The radiation levels reported at various facility locations are summarized in ORAUT-TKBS-0033. 

Table 7-7 summarizes the annual internal exposures due to residual radioactivity for the period of 

May 1, 1949, to December 31, 1993.

Table 7-7: Annual External Exposure to Residual Radioactivity 

Start End Exposure Basis R/y IREP Distribution 

05-01-49 12-31-49 Penetrating Survey Instrument 1.73E-2 Lognormal GSD 1.72 

01-01-50 12-31-93 Penetrating Survey Instrument 2.60E-2 Lognormal GSD 1.72 

05-01-49 12-31-49 Non-penetrating Survey Instrument 1.57E-1 Lognormal GSD 2.9 

01-01-50 12-31-93 Non-penetrating Survey Instrument 2.36E-1 Lognormal GSD 2.9 

7.3.3 Chapman Valve Occupational X-Ray Examinations 

Information regarding whether or not occupationally required medical X-ray examinations were 

performed at Chapman Valve is unavailable. The AEC usually, but not always, required 

“pre-employment” and periodic medical examinations of workers involved in the larger uranium 

processing programs. The term “pre-employment,” as used here, means prior to performing 

AEC-contracted radiological work. The typical AEC medical program included a preliminary and 

annual chest X-ray examination. This analysis assumes that workers received a pre-employment 

X-ray examination of the chest in 1947 and a second X-ray examination a year later. The method of 

X-ray examination should be based on current ORAU Team guidance for 1948 exposures. Organ 

doses can be obtained from the current revision of ORAUT-OTIB-0006, Technical Information 

Bulletin: Dose Reconstruction from Occupationally Related Diagnostic X-Ray Procedures. 

7.3.4 External Dose Reconstruction Feasibility Conclusion 

Adequate film badge results are available to estimate doses for Energy Employees who worked in the 

controlled area for the 1948 to 1949 period. The TBD provides an upper estimate of external dose 

based on film badge dosimetry records for unmonitored workers or unmonitored periods (ORAUTTKBS-0033). Based on the reviews and analyses of the available data and the TBD approach, the 

conclusion is that the Chapman Valve external monitoring data are sufficient to either: (1) estimate the 

maximum external radiation dose for every type of cancer for which radiation doses are reconstructed 

that could have been incurred under plausible circumstances by any member of the class; or (2) 

estimate the external radiation doses to members of the class more precisely than a maximum dose 

estimate. 
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7.4 Evaluation of Petition Basis for SEC-00043 

The following section evaluates the assertions made on behalf of petition SEC-00043 for the 

Chapman Valve Manufacturing Company. 

7.4.1 Evaluation of Specific Petitioner Statements in SEC-00043 

The following specific statements were made by workers on behalf of petition SEC-00043. The 

italicized statements are from the petition; the comments that follow are from NIOSH. 

7.4.1.1 Available Uranium Bioassay Data

SEC-00043: Bioassay data results (e.g., uranium in urine) are only available for three sets of 

dates during the Atomic Energy Commission’s contract period (January 1948 through April 

1949): 

• July 26-27, 1948, for a total of 22 workers (all but one were collected on the 27th) 

• September 8-9, 1948, for a total of six workers 

• October 7, 1948, for a total of five workers 

NIOSH analyzed four sets of samples in the development of the Chapman TBD dose reconstruction 

method. These samples included the three sets mentioned above as well as the set of bioassay 

samples taken after the fire (assumed to have occurred in early June, 1948, as addressed in the 

Chapman Valve TBD). The data are considered representative of the potential exposures from the 

uranium operations being performed by Chapman Valve because the bioassay samples were collected 

from employees accessing the restricted Chapman AEC areas in job categories that are considered 

representative of the workers involved in the AEC project. The bioassay data are consistent with the 

available Chapman air sample data, and with information from uranium operations at other sites. 

Bounding exposure scenarios were established in the Chapman Valve TBD through the application of 

overestimating assumptions, including: (1) the assumption of continuous chronic exposure over the 

entire operational period even though the majority of uranium machining appears to have been 

performed between May and November, 1948; and (2) the evaluation of internal exposures using the 

most claimant-favorable absorption type in the determination of organ dose. 

7.4.1.2 Uranium Bioassay Data Detection Limits

SEC-00043: Most of the bioassay results are at or below the limit of detection at that time 

(0.01 mg/l). NIOSH concedes in their April 22, 2005, memo to William Powers, Office of U.S. 

Representative Richard Neal, that they have no documentation about why these samples were 

collected.

During the development of the Chapman Valve TBD (ORAU-TKBS-0033), NIOSH analyzed 40 

urinalyses in the four sets of data discussed in Section 7.4.1.1 above. Urinalysis results ranged from 

<0.01 to 0.08 mg/L. Of these results, 55% (22 of the 40) are at or above the detection threshold of 

0.01 mg U/L. For those samples with values <0.01 mg U/L, knowledge of the detection threshold for 

the uranium analysis method that was applied permits the establishment of an upper bound of activity 
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for any sample result that was below that detection threshold which can then be applied in the 

reconstruction of dose in a claimant-favorable manner. This is because when an individual receives 

an internal exposure to uranium, the uranium will be excreted from the body in the urine for long 

periods after the exposure, generally in smaller concentrations over time as the amount of uranium in 

the body decreases (based on the clearance rate from the body). Each exposure that results in an 

intake contributes to the total amount of uranium in urine, so the amount of uranium in urine 

represents a long-term integration of all exposures that occurred prior to collection of the sample. 

Collection of bioassay samples by the Atomic Energy Commission (AEC) was a typical practice used 

to assess exposure conditions at sites. For a program of Chapman’s type (uranium metal handling), 

the available bioassay data, combined with a review of data from other sites, indicate that there is 

sufficient information to define uranium internal exposures. Although the exact selection criteria are 

unknown, it was standard for AEC to want to know what the worst-case exposures were so they could 

determine where additional controls might be most needed. Urine samples were collected from 

selected workers and analyzed for uranium. The NIOSH assumption applied in the development of 

the Chapman Valve TBD was that the July-through-October samples were routine bioassay samples. 

If these samples were incident-related, this assumption would result in intake estimates for the period 

that would be skewed higher because these would be the high samples; therefore, the chronic exposure 

assumption results in a more claimant-favorable approach. 

7.4.1.3 Estimation of an Upper Bound Dose

SEC-00043: There is insufficient bioassay data with which to estimate a plausible upper 

bound dose estimate for internal radiation exposures at Chapman Valve. Production process 

information is too limited to characterize exposures. Thus, the data that does exist is not 

representative of the potential exposures. There is only one day of air monitoring data. Thus, 

it is not feasible to estimate dose with sufficient accuracy.

NIOSH’s research during the development of the Chapman Valve TBD (ORAU-TKBS-0033) 

concluded that individual monitoring records do exist for Chapman Valve. The frequency of bioassay 

sampling for the uranium work was consistent with the application of bioassay sampling for the period 

evaluated, and it can be related to the application of then-current bioassay sampling programs at many 

sites. Based on the research performed, enough is known about the Chapman Valve production 

process to estimate exposures with sufficient accuracy for the proposed class. 

Air monitoring data are used in this radiological dose reconstruction program to estimate exposures 

when bioassay data are not available because bioassay data are better representations of worker 

exposures. Because Chapman Valve bioassay monitoring data are available, the air monitoring data 

were not used to reconstruct Chapman worker doses, as discussed in the Chapman Valve TBD. 

As previously discussed, the assumed operational exposure period ran from January 1, 1948, to April 

30, 1949. Although the information available on the operations at Chapman Valve indicate that the 

majority of machining and uranium-handling operations only occurred from May 1948, through 

November 1948, the Chapman Valve TBD analysis assumes the entire operational period to be the 

uranium intake period. In addition, two intake scenarios are provided for monitored and unmonitored 

workers. The first scenario accounts for exposure to the uranium fire in June 1948. The second 

scenario can be used when an individual had no exposure to the fire, or to supplement intake 
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determinations for workers whose bioassays are only associated with the fire. The data derived from 

this approach are similar to data from other sites performing similar operations during the same 

period. (NOTE: Y-12 was one of the larger sites involved in uranium-handling work during this time 

period and operations at that site included machining and lathing of uranium. A comparison of 

Chapman intakes with the Y-12 co-worker internal data analysis shows that the geometric means for 

Chapman’s type M intake rate is 63% of Y-12’s and Chapman’s type S intake rate is 140% of Y-12’s; 

the bioassay results also appear to be of similar magnitudes). 

7.4.1.4 Estimation of Uranium Exposures from a Site Fire

SEC-00043: Although seven workers were monitored after a documented uranium fire in May 

or June of 1948, the date of the fire is unknown. The monitoring was performed in early June. 

Because the dates of exposure(s) are unknown, the actual uranium uptakes are unknown. 

Chapman Valve(Fox, 1949) notes that: “A fire occurred in the restricted area of the AEC project and 

on June 11th [1948] urine for analyses ... was sent to the School of Medicine and Dentistry of 

Rochester New York.” The collection of urine samples from the workers who put out the fire, and 

from clean-up personnel, suggests that uranium was involved in the fire. NIOSH discovered no 

documentation that identified the exact date of the fire, although AEC (Wolf, 1949) noted in the 

transmittal of the urinalysis results that the samples had been “collected from the seven employees 

involved in the fire fighting episode last June [1948].” However, the actual Chapman Valve bioassay 

data were evaluated in bioassay models during the development of the Chapman Valve TBD dose 

reconstruction methodology to evaluate intake scenarios for deriving the best estimate of an intake 

date/period with final values that err in favor of the claimant. NIOSH based the final internal dose 

reconstruction method applied in the Chapman Valve TBD on their review of the data from this 

evaluation. 

7.4.1.5 Estimation of Enriched Uranium Exposures

SEC-00043: The Site Profile indicates that only natural uranium (0.7% U235) was used at Chapman 

Valve. It appears that, in addition to machining natural uranium, low enriched uranium was present. 

Oak Ridge National Laboratory (ORNL) found 2.16% enriched uranium in a Chapman site soil 

survey done for an environmental cleanup. 

The Chapman Valve uranium processing was related to reactor needs and the use of enriched uranium 

in reactors was rare until 1950. Specifically, Chapman Valve was contracted to machine uranium for 

the first Brookhaven National Laboratory test reactor (Brookhaven Graphite Research Reactor 

[BGRR]), a breeder reactor that first went critical in 1950, and was originally loaded with natural 

uranium. The only mentions of Chapman Valve and enriched uranium were in a 1997 ORNL survey 

report (ORNL/RASA-95/17), which reiterated a 1992 ORNL survey report (ORNL/RASA-92/1) that 

stated that the sample contained “slightly enriched (2.16%) Uranium-235.” The 1997 report attributed 

the small amount to background levels. Based on the review of the Chapman Valve site 

documentation, including the document that identified the single sample result of 2.16% enriched 

uranium (ORNL/RASA-92/1), NIOSH did not identify any other data to indicate that the uranium 

processed at Chapman Valve during the covered period was enriched, noting that, in 1948, enriched 

uranium was not typically sent to non-government-controlled sites without extra precautions. 
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A former Chapman Valve worker made a comment related to this subject indicating that there was the 

possibility of additional sources of radioactive material at Chapman Valve (i.e., a possible transfer 

point of manifolds from Oak Ridge for testing at Chapman Valve - Dean Street that may have 

contained enriched uranium). As discussed in Section 5.1, the DOE Office of Legacy Management 

performed additional research to determine whether radiological work was ever performed at the 

Chapman Valve - Dean Street location. The DOE concluded that no additional sources of radioactive 

materials were identified and no MED/AEC-related radiological work was performed at Chapman 

Valve (including Dean Street) other than what is currently listed by the DOE OWA. Therefore, for 

the purpose of this evaluation, DOE research provided no corroboration on the potential source of the 

enriched uranium identified in the single sample result. 

The conclusions of this review, and basis of the decision to apply natural uranium in the calculations, 

are included in the Chapman Valve TBD. However, this issue of uranium enrichment as is relates to 

dose evaluation at Chapman Valve does not have any bearing on the feasibility of dose reconstruction. 

It relates only to deciding on particular values to be used in dose calculations. 

7.4.1.6 Consideration of Other Industrial Processes

SEC-00043: The Site Profile does not assess exposures from a number of industrial processes, 

such as the cracking furnace or the uranium chip incinerator, and does not evaluate the 

potential for a uranium-rolling operation or the presence of low enriched uranium. The Site 

Profile indicated that: 

• the Chapman Valve . . . facility had a “cracking furnace.” 

• high uranium stack readings were measured on the roof. The purpose of the furnace was 

unknown to NIOSH and its use in the production operation is unknown to surviving workers. 

• a NIOSH/ORAU staffer was provided with a map prepared by ORNL showing the location of a 

chip burner. 

• air sample results from May 4 are measurements of the effluent from the furnace outlet on the roof 

and are not appropriate for determining workers’ doses. 

The AEC operations performed by Chapman Valve did not involve any material or chemical 

separation/conversion process. Therefore, any exposure issues associated with the work would have 

been due to only mechanical processing of the uranium. The uranium enrichment issues have been 

addressed in Section 7.4.1.5. 

The Chapman Valve TBD addresses individual exposures for all Chapman Valve operations. Based 

on the information provided in the Chapman Valve Final Remedial Action Report (Chapman, 1996), 

and during the Chapman Valve meetings, it is assumed that there was a furnace at Chapman Valve 

(also referred to as the chip incinerator, chip burner, and cracking furnace). On the map provided at 

the February 14, 2005, meeting, a chip burner is shown on the west side of Building 23 in an area 

consistent with the AEC restricted area. At what appears to be a similar location, ORNL/RASA-92/1 
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reported elevated contamination near a window. Robbins reported contamination was found in the 

area “where a chip burner was located in the southwest corner of Grid A-1 that exhausted to the 

atmosphere out a nearby window. The exhaust location and the shape of the roof of the building 

would lead to the deposition of more contamination on the south roof than the north roof as indicated 

by characterization measurements.” (Robbins, 1996) Because bioassay samples were collected from 

individuals working in the restricted area, the exposures from the incinerator would be reflected in the 

co-worker data. It seems most likely that the Heat Treater Foreman and some of the Helpers would 

have been involved with furnace work. 

The Chapman Valve TBD does address and evaluate the air sampling performed in the exhaust stack 

of the furnace. NUMEC 1966 and 1967 data regarding air concentrations and bioassays related to 

incinerator operations, referred to as “primitive” by NUMEC, were provided by attendees at the 

February 14, 2005, meeting. Although NUMEC appears to have handled primarily enriched uranium, 

and NUMEC 1960s operations might have been quite different than in 1948 at Chapman, comparisons 

can be made. The average breathing zone concentration at different NUMEC locations ranged from 

848 to 6666 pCi/m3 (these could be a factor of 2 to 100 lower when normalized for the difference in 

specific activity between the NUMEC and Chapman Valve uranium enrichments); these compare with 

calculated 95th percentile exposures of 139 to 4129 pCi/m3 from Chapman Valve co-worker bioassay 

results. The bioassay data for workers in the incinerator area at NUMEC were also available in the 

provided report and these, too, were considered. The reported NUMEC bioassay results ranged from 

37 to 68 ug/L assuming normal uranium, which would be 16 to 29 ug/L for 2% enriched uranium, and 

0.24 to 0.45 ug/L for 93.5% enriched uranium. 

Although NIOSH has not discovered information (either through document searches or worker 

interviews) that provides definitive information regarding the exact purpose of the furnace in 1948, it 

seems likely that it would have been used to oxidize (“roast”) uranium sweepings and turnings so they 

were converted to a more non-pyrophoric form that would be safer to store and ship. As previously 

stated, air monitoring data are used to estimate exposures when bioassay data are not available 

because bioassay data are better representations of worker exposures. Because Chapman Valve 

bioassay monitoring data are available, the air monitoring data were not used to reconstruct Chapman 

worker doses, as discussed in the Chapman Valve TBD. 

NIOSH has not identified evidence that AEC-contracted uranium-rolling operations were performed 

at Chapman Valve. A New York Operations Office (NYOO) Monthly Status and Progress Report 

indicates that Chapman was contracted by BNL to machine uranium for the BNL test reactor pile. 

The rods that Chapman machined came from Hanford (NYOO, 11-14-47). Note: The first BNL test 

reactor (Brookhaven Graphite Research Reactor [BGRR]) was a breeder reactor, originally loaded 

with natural uranium. A separate NYOO report does not include Chapman in the sites listed as 

performing uranium-rolling operations (NYOO, 11-12-48). Even if uranium-rolling operations were 

performed at Chapman Valve, the intakes still would have been accounted for by the bioassay data. 
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7.4.1.7 Available Air Sampling Data

SEC-00043: There is only one day of uranium air samples. Data was taken on 05/24/48. 

Data showed elevated levels of uranium, which raises questions about overall levels of 

uranium dust/smoke in the facility and the absence of contamination controls. 

It is true that workers were exposed to uranium dust at this facility and others. As discussed in this 

report, NIOSH has bioassay data from the workers which enable NIOSH to estimate the doses 

associated with these worker exposures and provide more accurate estimates of dose than would air 

monitoring data. The air monitoring data were not used to reconstruct Chapman worker doses, as 

discussed in the Chapman Valve TBD. 

7.4.1.8 Uranium Fires

SEC-00043: NIOSH does not assume any frequency for uranium fires in the site profile, even though 

documentation at other facilities shows that uranium fires are prevalent in uranium milling/lathing 

operations due to the fact that uranium is a pyrophoric material.

The June fire that occurred at Chapman was accounted for in the TBD through the use of individual 

bioassay results. These results are incident related and can be identified with the workers involved 

with the fire and cleanup. As previously discussed, samples were typically collected from workers 

thought to have the greatest likelihood of exposure. The NIOSH assumption applied in the 

development of the Chapman Valve TBD was that the July-through-October samples were routine 

bioassay samples. If these samples were incident-related, this assumption would result in intake 

estimates for the period that would be skewed higher because these would be the high samples; 

therefore, the NIOSH approach results in the most claimant favorable dose. 

7.5 Summary of Feasibility Findings for Petition SEC-00043 

This report evaluated the feasibility for completing dose reconstructions for employees at the 

Chapman Valve Manufacturing Company from January 1, 1948, through December 31, 1949, and 

from January 1, 1991, through December 31, 1993. It was determined that the available monitoring 

records, process descriptions, and source term data are sufficient to either: (1) estimate the maximum 

internal radiation dose for every type of cancer for which radiation doses are reconstructed that could 

have been incurred under plausible circumstances by any member of the class; or (2) estimate the 

internal radiation doses to members of the class more precisely than a maximum dose estimate. 

NIOSH did identify employees at the facility during this time period for which complete dose 

reconstruction would be feasible. 

It is important to note that the Chapman Valve TBD is currently being revised to reflect current 

NIOSH practices. In addition, the TBD will be revised to provide further clarification to issues 

identified by the petitioner, as appropriate. However, the technical changes being made to the TBD 

do not affect the conclusions in this evaluation report. 
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Table 7-8 summarizes the results of the feasibility findings at Chapman Valve for each exposure 

source for the time period January 1, 1948, through December 31, 1949, and from January 1, 1991, 

through December 31, 1993. 

Table 7-8: Summary of Feasibility Findings for SEC-00043 

Source of Exposure Maximum Exposure Can Be 

Determined 

Maximum Exposure Cannot 

Be Determined 

Internal X 

 - Urinalysis (in vitro) X 

External X 

 - Gamma X 

 - Beta X 

 - Occupational Medical x-ray X 

8.0 Evaluation of Health Endangerment for Petition SEC-00043 

The health endangerment determination for the class of employees covered by this evaluation report is 

governed by EEOICPA and 42 CFR § 83.13(c)(3). Under these requirements, if it is not feasible to 

estimate with sufficient accuracy radiation doses for members of the class, NIOSH must also 

determine that there is a reasonable likelihood that such radiation doses may have endangered the 

health of members of the class. This evaluation, however, determined that it is feasible to estimate 

with sufficient accuracy the radiation doses for members of this class. Therefore, a determination of 

health endangerment is not required. 

9.0 NIOSH Proposed Class for Petition SEC-00043 

Based on its research, NIOSH modified the petitioner-requested class to define a single class of 

employees for which NIOSH can estimate radiation doses with sufficient accuracy. The 

NIOSH-proposed class includes: All AWE employees who were monitored, or should have been 

monitored, for radiological exposures while performing Atomic Energy Commission work at the 

Chapman Valve Manufacturing Company (i.e., Building 23 and the Dean Street facility) in Indian 

Orchard, Massachusetts, from January 1, 1948 through December 31, 1949, and from January 1, 1991 

through December 31, 1993. 

For the purposes of this evaluation, the period from January 1, 1948, through April 30, 1949 is 

evaluated as the operational period; the periods from May 1, 1949, through December 31, 1949, and 

from January 1, 1991, through December 31, 1993, are evaluated as residual radioactivity periods. 

The latter time period of the petitioner-requested class was reduced from 1991 through 1995 to 1991 

through 1993 in order to expedite the evaluation of this SEC Petition. The period 1994 through 1995 

period will be evaluated as a Remediation Period. The remediation work was performed by Bechtel 

National, Inc. (BNI). Based on preliminary investigations of the remediation period, BNI had a fullyimplemented radiation protection program in place during the remediation work. The development of 

a dose reconstruction method for this period in the Chapman Valve Technical Basis Document has 
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been reserved pending further research. NIOSH is continuing to evaluate the 1994-1995 remediation 

period, and available data, for Chapman Valve and will address this period in an addendum to this 

Evaluation Report. 

These considerations are based on existing, approved NIOSH processes used in dose reconstruction 

for claims under EEOICPA. The guiding principle in conducting these dose reconstructions is to 

ensure that the assumptions used are fair, consistent, and well-grounded in the best available science. 

Simultaneously, uncertainties in the science and data must be handled to the advantage, rather than to 

the detriment, of the petitioners. When dose information is not available, or is very limited, NIOSH 

may use the highest reasonably possible radiation dose, based on reliable science, documented 

experience, and relevant data, to determine the feasibility of reconstructing the dose of an SEC 

petition class. NIOSH contends that it has complied with these standards of performance in 

determining that it would be feasible to reconstruct the dose for the class represented in this petition. 
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10.0 References 

42 CFR 81, Guidelines for Determining the Probability of Causation under the Energy Employees 

Occupational Illness Compensation Program Act of 2000; Final Rule, Federal Register/Vol. 67, No. 

85/Thursday, p 22296; May 2, 2002; SRDB Ref ID: 19391 

42 CFR 82, Methods for Radiation Dose Reconstruction under the Energy Employees Occupational 

Illness Compensation Program Act of 2000; Final Rule; May 2, 2002; SRDB Ref ID: 19392 

42 CFR 83, Procedures for Designating Classes of Employees as Members of the Special Exposure 

Cohort under the Energy Employees Occupational Illness Compensation Program Act of 2000; Final 

Rule; May 28, 2004; SRDB Ref ID: 22001 

42 USC §§ 7384-7385 [EEOICPA], Energy Employees Occupational Illness Compensation Program 

Act of 2000; as amended 

OCAS-PR-004, Internal Procedures for the Evaluation of Special Exposure Cohort Petitions, Rev. 0, 

National Institute for Occupational Safety and Health (NIOSH); Cincinnati, Ohio; September 23, 

2004 

ORAUT-OTIB-0004, Technical Information Bulletin: Estimating the Maximum Plausible Dose to 

Workers at Atomic Weapons Employer Facilities, Rev. 03, PC-1; November 18, 2005; SRDB Ref ID: 

19421 

ORAUT-OTIB-0006, Technical Information Bulletin: Dose Reconstruction from Occupationally 

Related Diagnostic X-Ray Procedures, Rev. 03, PC-1; December 21, 2005; SRDB Ref ID: 20220

ORAUT-TKBS-0033, Technical Basis Document: Exposure Matrix for Chapman Valve 

Manufacturing, Indian Orchard, Massachusetts, Period of Operation: January 4, 1948 through April 

30, 1949, Rev. 00; February 22, 2005; SRDB Ref ID: 19477 

ORNL/RASA-92/1, Results of the Independent Radiological Verification Survey at the Former 

Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts, July 1992; SRDB Ref ID 

6218 

ORNL/RASA-95/17, Results of the Independent Radiological Verification Survey at the Former 

Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts, May 1997; SRDB Ref ID 

6227 

AEC, 05-06-48, AEC-NYDO Sample Record #_, Radiological Laboratory; New York, New York; 

May 6, 1948; SRDB Ref ID: 16436 

AEC 06-01-48, AEC-NYDO Sample Record #4, Radiological Laboratory; New York, New York; June 

1, 1948; SRDB Ref ID: 16436 
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Chapman, 1943, Chapman Valve Order for U. S. Government Contract W-7412-ENG-1; November 

18, 1943; SRDB Ref ID: 6225 

Chapman, 1996, Chapman Valve Final Remedial Action Report; May 13, 1996; SRDB Ref ID: 13374 

Contracts, Partial list of contracts; SRDB Ref ID: 6239 (page 23) 

Crane, 1987, Request for Information from Crane Company on Chapman Site History; August 31, 

1987; SRDB Ref ID: 6239 

Dean, 2008, Letter reporting on DOE research results for Chapman Valve site, G. S. Podonsky (Chief 

Health, Safety and Security Officer; U.S. Department of Energy) to Larry Elliot (Director, Office of 

Compensation Analysis and Support; National Institute for Occupational Safety and Health); January 

7, 2008; OSA Ref ID: 10572 

Dvorak, 1987, Deposition on Crane Plant Site; December 8, 1987; SRDB Ref ID: 6230 

Electro, 1949, Chapman Valve Account, Electro Metallurgical Division U. C. & C. Corp. – Area 

Plant, Weekly Production Report: April 1 to April 30, 1949; SRDB Ref ID: 9036 

Fiore, 1987, Letter from J. J. Fiore to P. Hundt, Chief Counsel (Crane Company); no subject; U. S. 

Dept. of Energy; September 29, 1987; SRDB Ref ID: 6239 

Fox, 1949, Letter from G. E. Fox to B. S. Wolf, Medical Director (U.S. Atomic Energy Commission); 

no subject line; Page 3; Chapman Valve Manufacturing Company; Indian Orchard, Massachusetts; 

January 19, 1949; SRDB Ref ID: 12730 

LeVine, 1948, Letter from H. D. LeVine to V. T. Malcolm (Chapman Valve Company); Dust Sample 

Results; Radiological Laboratory; March 19, 1948; SRDB Ref ID: 6234 

Morgan, 1948, Letter from J. P. Morgan to G. E. Fox (Chapman Valve Mfg. Co.); Accounting for 

Source and Fissionable Material; Production Division, New York Operations; U. S. Atomic Energy 

Commission; August 24, 1948; SRDB Ref ID: 6222 

Morgan, 1949, Letter from J. P. Morgan to G. E. Fox (Chapman Valve Mfg. Co.); SF Material 

Reports; January 25, 1949; SRDB Ref ID: 6239 

Musgrave, 1948, Letter from T.P. Musgrave to H.D. LeVine, U.S. AEC; Film Badge Exposures, 

Chapman Valve Mfg. Co., Indian Orchard. Mass., H.K. Ferguson Co. at the Chapman Valve Mfg. 

Co.; May 24, 1948 (Page 4 of Chapman Valve_1948.pdf); SRDB Ref ID: 14131 

NYOO, 11-14-47, Monthly Status and Progress Report; Report for October, 1947; New York 

Operations Office; U. S. Atomic Energy Commission; November 14, 1947; SRDB Ref ID: 6292 

NYOO, 11-12-48, Monthly Status and Progress Report for October 1948; New York Operations 

Office; U. S. Atomic Energy Commission; November 12, 1948; SRDB Ref ID: 6287 
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Radiological Health, 1970, Radiological Health Handbook, Revised Edition; Public Health Service, 

U. S. Department of Health, Education, and Welfare; January 1970; publicly available 

Robbins, 1996, FUSRAP technical memorandum from R. Robbins to M. Redmon, Chapman Valve 

Final Remedial Action Report, Bechtel FUSRAP Project Job 14501, May 13, 1996; SRDB Ref ID: 

13374 

Sedelow, 1987, Letter to Crane Company, attention: Thomas J. Ungerland; no subject line; Crane 

Company, Indian Orchard Plant; November 19; SRDB Ref ID:13375 (page 5 of 14) 

Ungerland, 1987, Letter from T. J. Ungerland to J. J. Fiore; Attachment 1 – Crane Plant Site; 

September 29, 1987; SRDB Ref ID: 6230 

Urine, 1948, Urine Uranium Content, June 11, 1948, SRDB Ref ID: 6235 

Williams, Memo from Williams to Kelly; date unknown; SEC-00043 Supporting Documentation, 

Page 38; SECIS document ID 9178 

Williams, 1991, Letter from W. Alexander Williams to Anthony D. Pantaleoni; no subject line; Crane 

Company, the former Chapman Valve Manufacturing Company in Indian Orchard, Massachusetts; 

October 9, 1991; SRDB Ref ID: 6226 

Wilson, R. H., 1958, The Hanford Uranium Bio-Assay Program, Symposium on Occupational Health 

Experience and Practices in the Uranium Industry, HASL-58, U. S. Atomic Energy Commission, New 

York, New York, October 15 -17 [p. 87 of 001760.pdf] 

Wolf, 1947, Memo from B. S. Wolf to H. B. Fry, Staff Asst; Monthly Report; AECM-11 NY, U.S. 

Atomic Energy Commission; December 2, 1947; SRDB Ref ID: 6223 

Wolf, 01-21-48, Memo from B. S. Wolf to C. Slesser (Publications Branch); Weekly Activities Report 

– Period Jan. 15 to Jan. 21; AECM-11 NY; U.S. Atomic Energy Commission; January 21, 1948; 

SRDB Ref ID: 6232 

Wolf, 05-06-48, Memo from B. S. Wolf to C. Slesser (Publications Branch); Weekly Activities Report 

– Period April 28 to May 5; AECM-11 NY; U.S. Atomic Energy Commission; May 6, 1948; SRDB 

Ref ID: 6232 

Wolf, B.S., 1949, Letter to G. E. Fox (Chapman Valve Manufacturing Co.), no subject, U.S. Atomic 

Energy Commission, January 27, [p. 5 of 030000686.pdf] 

Young, 1987, Letter from C. D. Young to A. Wallo, III, U.S. DOE; Request for Information – Crane 

Company Sites; The Aerospace Corporation; Washington, D.C., August 31, 1987; SRDB Ref ID: 

6239